nuclear fuel rod reprocessing policy












http://www.chemcases.com/nuclear/nc-13.htm
Chemical Processes and Nuclear Reactor Fuel

Nuclear Chemistry
Recycling Spent Reactor Fuel

Dr. Frank Settle

There are about 557 nuclear power reactors in the world and about 440 are operating in early 2005.  These reactors have common elements that uranium oxide enriched to 3-4% 235U is fabricated into pellets then inserted into fuel rods.  These rods are neutron emitters and, in close proximity with each other, begin a self-sustaining chain reaction releasing energy and producing new elements by the fission of the uranium and producing plutonium (239Pu) by nuclear chain reactions. These fuel rods generally can supply energy from the fission reaction for 1-3 years.  They are then removed and replaced by new rods.

Spent fuel from nuclear reactors still contains considerable amounts of 235 U but now has generated significant 239Pu.  After 3 years in a reactor, 1,000 lbs. of 3.3-percent-enriched uranium (967 lbs. 238 U and 33 lbs. 235U) contain 8 lbs. of 235U and 8.9 lbs. of plutonium isotopes along with 943 lbs. of 238U and assorted fission products. Separating the 235U and 239Pu from the other components of spent fuel significantly addresses two major concerns. It greatly reduces the long-lived radioactivity of the residue and it allows purified 235U and 239Pu to be used as reactor fuel. (Courtesy of the Uranium Information Center)

 

Three options are available for cooled spent fuel rods; they can remain at the sites from which they have been removed from service, be moved to a more permanent site for storage or they can be reprocessed to remove the uranium and plutonium. In either case, these fuel rods must cool in storage ponds near the reactor for several months in order to reduce their short-lived radioactivity and to allow them to dissipate their initial high thermal energy. Reprocessing involves chopping up the fuel rods and dissolving the pieces. 

The plutonium and uranium are then removed and chemically  separated.  The byproducts of reprocessing, transuranic elements and fission products can be encapsulated in glass and disposed as waste. Gaseous diffusion or other processes can be used to enrich the uranium. The plutonium can be mixed with enriched uranium to make mixed oxide (MOX) reactor fuel. Purified plutonium can also be used for nuclear weapons. Great Britain and France have built large reprocessing plants to produce MOX fuel. They reprocess spent fuel not only from reactors in their respective countries, but also from reactors in other nations.

At one time, the United States planned to use a plutonium-uranium extraction (PUREX) process to for this separation.  But no spent fuel from nuclear power plants has been  reprocessed in the US.  In 1977 President Carter established national policy that prohibited reprocessing based on the premise that limiting plutonium would limit the spread of nuclear weapons around the world.  Although President Reagan reversed this policy, reprocessing has never been initiated in the US.

But in science, what can be done, will be done.  Local policy seldom deters the ambitions of the entire environment.

The French have reprocessed power plant spent fuel rods at the COGEMA LaHague site since 1966.  The French see reprocessing as ecologically sound, economical and profitable and as demonstrating scientific leadership on a world stage.

Quite naturally, the rise of organized terrorism since about 1990, culminating in the destruction of the Twin Towers in New York has focused attention on all aspects of nuclear material management.  As an example, the LaHague site was surrounded for a time by antiaircraft missiles for a time after the 2001 terrorist attacks.

In the US spent rods are currently stored at locations near the approximately 70 plants throughout the country. US fuel rod disposal planning anticipates opening a facility at Yucca Mountain, NV by 2012 for permanent burial of spent rods.

(Courtesy of the Department of Energy)

Complete Bibliography on Nuclear Power , Nuclear Waste  and Reprocessing from the ALSOS Digital Library for Nuclear Issues




http://www.pbs.org/newshour/updates/northkorea_10-02-03.html








Korean Peninsula October 2, 2003, 1:25pm EDT
NORTH KOREA SAYS FUEL RODS PROCESSED FOR NUCLEAR BOMBS

North Korea said Thursday it had processed some 8,000 spent fuel rods that could be used to make atomic bombs, another in a series of moves in the ongoing nuclear standoff with Pyongyang.

NewsHour Links

Online NewsHour Special Report:
North Korea: Nuclear Standoff



A statement issued by the North Korean Foreign Ministry said it would continue to pursue its nuclear program because of the "hostile policy" of the United States toward the communist North.

"(North Korea) successfully finished the reprocessing of some 8,000 spent fuel rods," said the statement, published by the official KCNA news agency. U.S. Secretary of State Colin Powell said Thursday the United States has no evidence North Korea has reprocessed the spent nuclear fuel rods."This is the third time they have told us they have just finished reprocessing the rods. We have no evidence to confirm that," Powell said at a news briefing. Pyongyang has pointed to the so-called "hostile" policy of the United States as a key reason for its January withdrawal from the Nuclear Non-Proliferation Treaty and its decision to expel U.N. inspectors from its nuclear facilities.North Korea has said before that it completed reprocessing its pool of spent rods, but Thursday marked the first time it claimed to be using plutonium gathered from the rods to make nuclear weapons. The country's recent claims about its nuclear developments have not been independently confirmed."We will reprocess more spent fuel rods to be churned out in an unbroken chain from the 5 mw (megawatt) nuclear reactor in Yongbyon without delay when we deem it necessary," the statement said, referring to the North's nuclear plant.The statement also said North Korea "made a switchover in the use of plutonium churned out by reprocessing spent fuel rods in the direction (of) increasing its nuclear deterrent force." Analyses by diplomats and regional observers indicate that the North's statement fits a pattern of tactics intended to help its negotiating position in international talks."This is what North Korea always does before negotiating," Jin Canrong, an international relations expert at the People's University in Beijing, told Reuters. "They throw out a few new balls."The North's statement dismissed as groundless reports that more international talks could be held soon, similar to the six-way summit on the North's nuclear program held in late August by North and South Korea, Japan, the United States, Russia and China.But the North notably did not rule out the possibility for more talks altogether in its statement.South Korean Vice Unification Minister Cho Kun-shik said at a briefing in Seoul the North would respond to future calls for new talks."They are not in a position to oppose talks," he said.South Korea's Foreign Ministry urged the North in a statement not to take steps that would further escalate the situation."The North's announcement was very regrettable," South Korean Foreign Ministry spokesman Shin Bong-kil said. "We are deeply concerned it not only undermines inter-Korean relations and efforts for the peaceful resolution of the nuclear issues but hurts the atmosphere for dialogue set by the previous talks."In his comments to reporters, Powell called on the North's neighbors to urge it to abandon its nuclear ambitions. "North Korea's neighbors should also be delivering a message to Kim Jong Il that the solution to the problem is for them to stop moving in this direction (and to) continue to participate in the diplomacy that is under way," Powell said. U.S. intelligence analysts have expressed concern that North Korea might have three, four or even six nuclear weapons instead of the one or two the Central Intelligence Agency now estimates, according to an Associated Press report. Powell said the United States was still willing to consider some security guarantees to ease the nuclear tensions with the North."We are examining ways ... to provide the kinds of security assurances that might help to move the process further along," he said. "We will continue to pursue diplomacy." The reprocessing of 8,000 rods could yield enough material to create 20 nuclear bombs, Yu Suk-ryul, a professor at the Institute of Foreign Affairs and National Security in Seoul, told Reuters. But he said North Korea did not have the expertise to produce that many bombs -- perhaps five or six in about six months.







Information Papers

Processing of Used Nuclear Fuel for Recycle 

(October 2008)

The availability of recyclable fissile and fertile materials able to provide fresh fuel for existing and future nuclear power plants is a key, nearly unique, characteristic of nuclear energy. In many countries government policies have not yet addressed the various aspects of this feature.

Over the last fifty years the principal reason for reprocessing used fuel has been to recover unused uranium and plutonium in the used fuel elements and thereby close the fuel cycle, gaining some 25% more energy from the original uranium in the process and thus contributing to energy security.  A secondary reason is to reduce the volume of material to be disposed of as high-level waste to about one fifth.  In addition, the level of radioactivity in such 'light' waste is much smaller and after about 100 years falls much more rapidly than in used fuel itself.  Reprocessing has been the government policy in many European countries, Russia and Japan.

In the last decade interest has grown in recovering all long-lived actinides together (ie with plutonium) so as to recycle them in fast reactors so that they end up as short-lived fission products.  This policy is driven by two factors: reducing the long-term radioactivity in high-level wastes, and reducing the possibility of plutonium being diverted from civil use, ie increasing proliferation resistance of the fuel cycle.  Starting in 2005 this interest in more fully closing the fuel cycle has grown and became more public.  The use of fast reactors has the considerable additional benefit of greatly extending uranium resources, in that very much more energy can be obtained from them.

Reprocessing used fuel* to recover uranium (U, as RepU) and plutonium (Pu) avoids the wastage of a valuable resource. Most of it - about 96% - is uranium at less than 1% U-235 (often 0.4 - 0.8%), and up to 1% is plutonium. Both can be recycled as fresh fuel, saving up to 30% of the natural uranium otherwise required. The materials potentially available for recycling (but locked up in stored used fuel) could conceivably run the US reactor fleet of about 100 GWe for almost 30 years with no new uranium input.

* Used fuel from light water reactors (at normal US burn-up) contains approximately:
95.6% uranium (U-232 0.1-0.3%, U-234 0.1-0.3%, U-235 0.5-1.0%, U-236 ).4-0.7%, balance: U-238)
2.9% stable fission products
0.9% plutonium
0.3% cesium & strontium (fission products)
0.1% iodine and technetium (fission products)
0.1% other long-lived fission products
0.1% minor actinides (americium, curium, neptunium)

Reprocessing also avoids leaving the plutonium in the used fuel, where in a century or two the built-in radiological protection will have diminished, allowing it to be recovered for illicit use (though it is unsuitable for weapons due to the non-fissile isotopes present).

 

World Commercial Reprocessing Capacity

(tonnes per year)
LWR fuel: France, La Hague
1700

UK, Sellafield (THORP)
900

Russia, Ozersk (Mayak)
400

Japan (Rokkasho)
800

total approx
3800
Other nuclear fuels: UK, Sellafield
1500

India
275

total approx
1750
Total civil capacity  
5550
Sources: OECD/NEA 2006 Nuclear Energy Data, Nuclear Eng. International handbook 2007.
 

So far, almost 90,000 tonnes (of 290,000 t discharged) of used fuel from commercial power reactors has been reprocessed for U & Pu recovery. Annual reprocessing capacity is now some 4000 tonnes per year for normal oxide fuels, but not all of it is operational.

By 2030 some 400,000 tonnes of used fuel is expected to be generated worldwide (from 2008), including 60,000 t in North America and 69,000 t in Europe.  Recycling centres envisaged could each process 2500 t/yr of this and produce 300 tonnes of MOX.

Most of the separated uranium (RepU) remains in storage, though its conversion and re-enrichment (in UK, Russia and Netherlands) has been demonstrated, along with its re-use in fresh fuel. Some 16,000 tonnes of RepU from Magnox reactors* in UK has been used to make about 1650 tonnes of enriched AGR fuel.  Higher assay material (c 0.9% U-235) from THORP reprocessing will be used in the next Sizewell B reload.  In Belgium, France, Germany and Switzerland over 8000 tonnes of RepU has been recycled into nuclear power plants.  In Japan the figure is over 335 tonnes in tests and in India about 250 t of RepU has been recycled into PHWRs.  Allowing for impurities affecting both its treatment and use, RepU value has been assessed as about half that of natural uranium.

* since Magnox fuel was not enriched in the first place, this is actually known as Magnox depleted uranium (MDU).  It assayed about 0.4% U-235 and was converted to UF6, enriched to 0.7% at BNFL's Capenhurst diffusion plant and then to 2.6% to 3.4% at Urenco's centrifuge plant.  Until the mid 1990s some 60% of all AGR fuel was made from MDU and it amounted to about 1650 tonnes of LEU.  Recycling of MDU was discontinued in 1996 due to economic factors.

Most of the separated plutonium is used almost immediately in mixed oxide (MOX) fuel. The higher the burn-up levels, the less value is the plutonium, due to increasing proportion of non-fissile isotopes and minor actinides and depletion of fissile plutonium isotopes.

Reprocessing policies

Conceptually reprocessing can take several courses, separating certain elements from the remainder, which becomes high-level waste:

* Minor actinides are americium and curium (95 & 96 in periodic table), sometimes also neptunium (93). (The major actinides are plutonium - #94 and uranium - #92)

In today's reactors, recycled uranium needs to be enriched, whereas plutonium goes straight to mixed oxide (MOX) fuel fabrication. This situation has two perceived problems: the separated plutonium is sometimes considered a proliferation risk, and the minor actinides remain in the separated waste, which means that its radioactivity is longer-lived than if it comprised fission products only.

For the future, the focus is on removing the actinides from the final waste and burning them with the recycled uranium and plutonium in fast neutron reactors. The longer-lived fission products may also be separated from the waste and transmuted in some other way.

All but one of the six Generation IV reactors being developed have closed fuel cycles which recycle all the actinides. Although US policy has been to avoid reprocessing, the US budget process for 2006 included $50 million to develop a plan for "integrated spent fuel recycling facilities", and a program to achieve this with fast reactors has become more explicit since.

In November 2005 the American Nuclear Society released a position statement saying that it "believes that the development and deployment of advanced nuclear reactors based on fast-neutron fission technology is important to the sustainability, reliability and security of the world's long-term energy supply." This will enable "extending by a hundred-fold the amount of energy extracted from the same amount of mined uranium". The statement envisages on-site reprocessing of used fuel from fast reactors and says that "virtually all long-lived heavy elements are eliminated during fast reactor operation, leaving a small amount of fission product waste which requires assured isolation from the environment for less than 500 years."

Products of reprocessing

The composition of reprocessed uranium (RepU) depends on the initial enrichment and the time the fuel has been in the reactor, but it is mostly U-238.  It will normally have less than 1% U-235* and also smaller amounts of U-232 and U-236 created in the reactor.  The U-232, though only in trace amounts, has daughter nuclides which are strong gamma-emitters, making the material difficult to handle, though in the reactor U-232 is no problem (it captures a neutron and becomes fissile U-233).  It is largely formed through alpha decay of Pu-236, and the concentration of it peaks after about 10 years of storage. 

* Typical value today about 0.3% U-235.

The U-236 is a neutron absorber present in much larger amounts, typically 0.4% to 0.6% - more with higher burn-up, which means that if reprocessed uranium is used for fresh fuel it must be enriched significantly (eg one tenth) more than is required for natural uranium.  Thus RepU from low-burn-up fuel is more likely to be suitable for re-enrichment, while that from high burn-up fuel is best used for blending or MOX fabrication. 

The other minor uranium isotopes are U-233 (fissile), U-234 (from original ore, enriched with U-235, fertile), and U-237 (short half-life beta emitter).  None of these affects the use of handling of the reprocessed uranium significantly.In the future, laser enrichment techniques may be able to remove these isotopes. 

Reprocessed uranium (especially from earlier military reprocessing) may also be contaminated with traces of fission products and transuranics.  This will affect its suitability for recycling either as blend material or via enrichment.  Over 2002-06 USEC successfully cleaned up 7400 tonnes of technetium-contaminated uranium from the US Department of Energy. 

About 2000 to 2500 tonnes per year of RepU is currently used for fuel.  The remainder is stored.  Reprocessing of 850 tonnes of French used LWR fuel per year (about 15 years after discharge) yields 810 tonnes of reprocessed uranium (RepU).  Of this about two thirds is converted into stable oxide form for storage. One third of the RepU is re-enriched and EdF has demonstrated its use in 900 MWe power reactors. 

The separated plutonium from reprocessing will have an isotopic concentration determined by the fuel burn-up level.  At anything over about 20 GWday/t burn-up this will be "reactor grade" and significantly different from weapons grade material.*  Whether this plutonium is separated on its own or with other actinides is a major policy issue relevant to reprocessing - see sections below.

* Some figures for Oskarshamn-3: with 30 GWd/t burn-up: 69% Pu is fissile, 40 GWd/t 61% fissile, 50 GWd/t: 55% fissile and 60 GWD/t: 50% fissile.

Reprocessing of 850 tonnes of EdF used fuel per year (about 15 years after discharge) produces 8.5 tonnes of plutonium (immediately recycled as 100 tonnes of MOX) and 810 tonnes of reprocessed uranium (RepU).  Of this about two thirds is converted into stable oxide form for storage. One third of the RepU is re-enriched at Pierrelatte and EdF has demonstrated its use of in 900 MWe power reactors.

World MOX production capacity in 2008 is a little over 200 tonnes per year, mostly in France, and this utilises about one third of the annual amount of plutonium separated in reprocessing plants.  In 2007 EdF said that the plutonium stored at Areva's La Hague from reprocessing could provide the start-up fuel for seven Generation IV fast reactors, with 15 tonnes for each.

Inventory of Separated Recyclable Materials

 

  Quantity - tonnes   Natural U equivalent - tonnes  

Plutonium from reprocessed fuel

 320  60,000
Uranium from reprocessed fuel   45,000  50,000
Ex-military plutonium   70 15,000 
Ex-military high-enriched uranium   230   70,000

 

Source: NEA 2007. 

Storage of used fuel 

Used fuel assemblies removed from a reactor are very radioactive and produce heat.  They are therefore put into large tanks or "ponds" of water which cool them, and three metres of water over them shields the radiation.  Here they remain, most at the reactor site or otherwise at a central storage facility or at the reprocessing plant, for a number of years as the level of radioactivity decreases considerably.  For most types of fuel, reprocessing occurs anything from 5 to 25 years after reactor discharge.

History of reprocessing, US policy change

 A great deal of hydrometallurgical reprocessing has been going on since the 1940s, originally for military purposes, to recover plutonium for weapons*. In the UK, metal fuel elements from the first generation gas-cooled commercial reactors have been reprocessed at Sellafield for about 50 years. The 1500 t/yr Magnox plant undertaking this has been successfully developed to keep abreast of evolving safety, hygiene and other regulatory standards. From 1969 to 1973 oxide fuels were also reprocessed, using part of the plant modified for the purpose. A new 900 t/yr thermal oxide reprocessing plant (THORP) was commissioned in 1994 and the corresponding mixed oxide (MOX) fuel plant in 2001.

* from low burn-up used fuel, which has been in a reactor for only a very few months.

In the USA, no civil reprocessing plants are now operating, though three have been built. The first, a 300 t/yr plant at West Valley, NY, was operated successfully from 1966-72. However, escalating regulation required plant modifications which were deemed uneconomic, and the plant was shut down. The second was a 300 t/yr plant built at Morris, Illinois, incorporating new technology which, although proven on a pilot-scale, failed to work successfully in the production plant. It was declared inoperable in 1974. The third was a 1500 t/yr plant at Barnwell, South Carolina, which was aborted due to a 1977 change in government policy which ruled out all US civilian reprocessing as one facet of US non-proliferation policy. In all, the USA has over 250 plant-years of reprocessing operational experience, the vast majority being at government-operated defence plants since the 1940s.

In France a 400 t/yr reprocessing plant operated for metal fuels from gas-cooled reactors at Marcoule until 1997.  At La Hague, reprocessing of oxide fuels has been done since 1976, and two 800 t/yr plants are now operating, giving overall capacity of 1700 t/yr.  India has a 100 t/yr oxide fuel plant operating at Tarapur with others at Kalpakkam and Trombay, and Japan is starting up a major (800 t/yr) plant at Rokkasho while having had most of its used fuel reprocessed in Europe meanwhile. It had a small (90 t/yr) plant operating at Tokai Mura. Russia has a 400 t/yr oxide fuel reprocessing plant at Ozersk (Chelyabinsk).

In France EdF has made provision to store reprocessed uranium (RepU) for up to 250 years as a strategic reserve. Currently, reprocessing of 1150 tonnes of EdF used fuel per year produces 8.5 tonnes of plutonium (immediately recycled as mixed oxide - MOX - fuel) and 815 tonnes of RepU. Of this about 650 tonnes is converted into stable oxide form for storage. EdF has demonstrated the use of RepU in its 900 MWe power plants, but it is currently uneconomic due to conversion costing three times as much as that for fresh uranium, and enrichment needing to be separate because of U-232 and U-236 impurities (the former gives rise to gamma radiation, the latter means higher enrichment is required).

As noted above, the USA has considerable reprocessing experience but application of this to civil used fuel has been frustrated by political sensitivities motivated by proliferation concerns based on a perception that reactor-grade plutonium is usable for weapons. Civil reprocessing was stopped in 1977.

In February 2006 the US government announced the Global Nuclear Energy Partnership (GNEP) through which it "will work with other nations possessing advanced nuclear technologies to develop new proliferation-resistant recycling technologies in order to produce more energy, reduce waste and minimise proliferation concerns." GNEP goals include reducing US dependence on imported fossil fuels, and building a new generation of nuclear power plants in the USA. Two significant new elements in the strategy are new reprocessing technologies at Advanced Recycling Centres (not "reprocessing plants") which separate all transuranic elements together (and not plutonium on its own) ­ starting with the UREX+ process, and Advanced Burner (fast) Reactors to consume the result of this while generating power.

In mid 2006 a report by the Boston Consulting Group for Areva and based on proprietary Areva information showed that recycling used fuel in the USA using the COEX aqueous process would be economically competitive with direct disposal of used fuel. A $12 billion, 2500 t/yr plant was considered, with total capital expenditure of $16 billion for all related aspects. This would have the benefit of greatly reducing demand on space at the Yucca mountain repository.

Boston Consulting gave four reasons for reconsidering US used fuel strategy which has applied since 1977:

Soon after this the US Department of Energy said that it might start the GNEP program using reprocessing technologies that "do not require further development of any substantial nature" such as COEX while others were further developed. It also flagged detailed siting studies on the feasibility of this accelerated "development and deployment of advanced recycling technologies by proceeding with commercial-scale demonstration facilities."

Reprocessing today - PUREX 

All commercial reprocessing plants use the well-proven hydrometallurgical PUREX * process.  This involves dissolving the fuel elements in concentrated nitric acid.  Chemical separation of uranium and plutonium is then undertaken by solvent extraction steps (neptunium**  can also be recovered if required).  The Pu and U can be returned to the input side of the fuel cycle - the uranium to the conversion plant prior to re-enrichment and the plutonium straight to MOX fuel fabrication. 

*  Plutonium URanium EXtraction

** may be used for producing Pu-238 for thermo-electric generators for spacecraft.

Alternatively, some small amount of recovered uranium can be left with the plutonium which is sent to the MOX plant, so that the plutonium is never separated on its own.  This is known as COEX ** process, developed in France as a "Generation III" process, but not yet in use (see next section). 

 ** CO-EXtraction of actinides

At Japan's new Rokkasho plant a modified PUREX process is used to achieve a similar result by recombining some uranium before co-denitration, with the main product being 50:50 mixed oxides..

In either case, the remaining liquid after Pu and U are removed is high-level waste, containing about 3% of the used fuel in the form of fission products and minor actinides (Np, Am, Cm). It is highly radioactive and continues to generate a lot of heat. It is conditioned by calcining and incorporation of the dry material into borosilicate glass, then stored pending disposal. In principle any compact, stable, insoluble solid is satisfactory for disposal.

After reprocessing, the recovered uranium may be handled in a fuel fabrication plant (after re-enrichment)*, but the plutonium must be recycled via a dedicated mixed oxide (MOX) fuel fabrication plant. In France the reprocessing output is co-ordinated with MOX plant input, to avoid building up stocks of plutonium.**

* Recycled uranium must be handled in dedicated facilities because gamma-emitting uranium isotopes mean it requires shielding and neutron-absorbing isotopes mean that a higher level of enrichment is required compared with fresh uranium.

** If plutonium is stored for some years the level of Americium-241, the isotope used in household smoke detectors, will accumulate and make it difficult to handle through a MOX plant due to the elevated levels of gamma radioactivity.

Developments of PUREX

Another version of PUREX has the minor actinides (americium, neptunium, curium) being separated in a second aqueous stage and then directed to an accelerator-driven system cycling with pyroprocessing for transmutation (see later sections).  The waste stream then contains largely fission products.

The PUREX process and its derivatives may also be supplemented to recover fission products - iodine by volatilisation, and technetium by electrolysis.  The US UREX+ processes allows recovery of iodine and technetium at the head end.  French CEA research has shown 95% and 90% recoveries respectively.  The same research effort has demonstrated separation of caesium.

Energy Solutions Inc holds the rights to PUREX in the USA and has developed NUEX, which separates uranium and then all transuranics (including plutonium) together, with fission products separately.

Other variations of PUREX are being developed by the US Department of Energy for civil wastes.  In these, only uranium is recovered initially for recycle (hence UREX+ processes).  The residual is treated to recover plutonium with other transuranics for recycling in fast reactors.  The fission products then comprise most of the high-level waste.  The central feature of this system is to keep the plutonium with other transuranics which are destroyed by burning in a fast neutron reactor. 

A version of UREX+ was demonstrated with used fuel in 2005 at the Argonne National Laboratory, including separate recovery of technetium.  As of mid 2007 several variations of UREX+ have been developed, with the differences being in how the plutonium is combined with various minor actinides, and lanthanide and non-lanthanide fission products are combined or separated.  UREX+1a combines plutonium with three minor actinides, but this gives rise to problems in fuel fabrication due to americium being volatile and curium a neutron emitter.  UREX+3 leaves only neptunium with the plutonium and the result is closer to a conventional MOX fuel and hence more easily qualified by NRC.  However, it is less proliferation-resistant than UREX+1a.

Areva and CEA have developed three processes on the basis of extensive French experience with PUREX:

All three processes are to be assessed in 2012, so that two pilot plants can be built to demonstrate industrial scale potential:

In the longer term the goal is to have a technology validated for industrial deployment of Gen IV fast reactors about 2040, at which stage the present La Hague plant will be due for replacement. 

Another process being developed by Mitsubishi and Japanese R&D establishments as a corollary of fast reactor advanced fuel cycle is Super-DIREX (Supercritical fluid Direct Extraction).  This is designed to cope with MOX fuels from light water and fast reactors.  The fuel fragments are dissolved in nitric acid with tributyl phosphate and supercritical CO2, simplifying the aqueous stream.  This results in uranium and actinides complexing with TBP, leaving solid and some aqueous wastes.

Partitioning goals

Several factors give rise to a more sophisticated view of reprocessing today, and use of the term partitioning reflects this. First, new management methods for high and intermediate-level nuclear wastes are under consideration, notably partitioning-transmutation (P&T) and partitioning-conditioning (P&C), where the prime objective is to separate long-lived radionuclides from short-lived ones.  Secondly, new fuel cycles such as those for fast neutron reactors (including a lead-cooled one) and fused salt reactors, and the possible advent of accelerator-driven systems, require a new approach to reprocessing. Here the focus is on electrolytic processes ('pyroprocessing') in a molten salt bath.  The term electrometallurgical is also increasingly used of this in the USA.

The main radionuclides targeted for separation for P&T or P&C are the actinides neptunium, americium and curium (along with U & Pu), and the fission products iodine (I-129), technetium (Tc-99), caesium (Cs-135) and strontium (Sr-90). Removal of the latter two significantly reduces the heat load of residual conditioned wastes. In Japan, platinum group metals are also targeted, for commercial recovery. Of course any chemical process will not discriminate different isotopes of any element.

Efficient separation methods are needed to achieve low residuals of long-lived radionuclides in conditioned wastes and high purities of individual separated ones in transmutation targets . Otherwise any transmutation effort is a random process with uncertain results. In particular one does not want fertile uranium isotopes (eg U-238) in a transmutation target with slow neutrons, or neutron capture will be the main action and hence it will generate further radiotoxic transuranic isotopes.

Achieving effective full separation for any transmutation program is likely to mean electrolytic processing of residuals from the PUREX or similar aqueous processes.

A BNFL-Cogema study in 2001 reported that 99% removal of actinides, Tc-99 & I-129 would be necessary to justify the effort in reducing the radiological load in a waste repository. A U.S. study identified a goal of 99.9% removal of the actinides and 95% removal of technetium and iodine. In any event, the balance between added cost and societal benefits is the subject of considerable debate.

Electrometallurgical "Pyro-processing"

Electrolytic / electrometallurgical processing techniques ('pyroprocessing') to separate nuclides from a radioactive waste stream have been under development in the USA Department of Energy laboratories, notably Argonne, as well as by the Korea Atomic Energy Research Institute (KAERI) in conjunction with work on DUPIC (see section below).

So-called pyroprocessing involves several stages: volatilisation, liquid-liquid extraction using immiscible metal-metal phases or metal-salt phases, electrolytic separation in molten salt, fractional crystallisation, etc. They are generally based on the use of either fused (low-melting point) salts such as chlorides or fluorides (eg LiCl+KCl or LiF+CaF2) or fused metals such as cadmium, bismuth or aluminium. They are most readily applied to metal rather than oxide fuels, and are envisaged for fuels from generation IV reactors.

Electrometallurgical 'Pyroprocessing' can readily be applied to high burn-up fuel and fuel which has had little cooling time, since the operating temperatures are high already. However, such processes are at an early stage of development compared with hydrometallurgical processes already operational.

Separating (partitioning) the actinides contained in a fused salt bath is by electrodeposition on a cathode, so involves all the positive ions without the possibility of chemical separation of heavy elements such as in Purex and its derivatives.  This cathode product can then be used in a fast reactor, since it is not sensitive to small amounts of impurities. 

GE Hitachi Nuclear Energy (GEH) is developing this Advanced Recycling Centre concept which combines electrometallurgical separation and burning the final product in one or more of its PRISM fast reactors on the same site.  The first two stages of the separation remove uranium which is recycled to light water reactors, then fission products which are waste, and finally the actinides including plutonium.

So far only one pyroprocessing technique has been licensed for use on a significant scale. This is the IFR (integral Fast Reactor) electrolytic process developed by Argonne National Laboratory in the USA and used for pyroprocessing the used fuel from EBR-II experimental fast reactor which ran from 1963-1994. This application is essentially a partitioning-conditioning process, because neither plutonium nor other transuranics are recovered for recycle. The process is used to facilitate the disposal of a fuel that could not otherwise be sent directly to a geologic repository. The uranium metal fuel is dissolved in LiCl+KCl molten bath, the U is deposited on a solid cathode, while the stainless steel cladding and noble metal fission products remain in the anode, and are consolidated by melting to form a durable metallic waste. The transuranics and fission products in salt are then incorporated into a zeolite matrix which is hot pressed into a ceramic composite waste. The highly-enriched uranium recovered from the EBR-II driver fuel is down-blended to less than 20% enrichment and stored for possible future use.

The PYRO-A process, being developed at Argonne to follow the UREX process, is a pyrochemical process for the separation of transuranic elements and fission products contained in the oxide powder resulting from denitration of the UREX raffinate. The nitrates in the residual raffinate acid solution are converted to oxides, which are then reduced electrochemically in a LiCl-Li2O molten salt bath. The more chemically active fission products (e.g., Cs, Sr) are not reduced and remain in the salt. The metallic product is electrorefined in the same salt bath to separate the transuranic elements on a solid cathode from the rest of the fission products. The salt bearing the separated fission products is then mixed with a zeolite to immobilize the fission products in a ceramic composite waste form. The cathode deposit of transuranic elements is then processed to remove any adhering salt and is formed into ingots for subsequent fabrication of transmutation targets.

The PYRO-B process, has been developed for the processing and recycle of fuel from a transmuter (fast) reactor. A typical transmuter fuel is free of uranium and contains recovered transuranics in an inert matrix such as metallic zirconium. In the PYRO-B processing of such fuel, an electrorefining step is used to separate the residual transuranic elements from the fission products and recycle the transuranics to the reactor for fissioning. Newly-generated technetium and iodine are extracted for incorporation into transmutation targets, and the other fission products are sent to waste.

The KAERI advanced spent fuel conditioning process - ACP involves separating uranium, transuranics including plutonium, and fission products including lanthanides.  It utilises a high-temperature lithium-potassium cathode.  Development of this process is at the heart of US-South Korean nuclear cooperation, and will be central to the renewal of the US-ROK agreement in 2014, so is already receiving considerable attention in negotiations.  Much of the R&D has been done in the USA, based on earlier US work in 1970s, but paid for by KAERI.  However, the US government suspended this.  South Korea has declined an approach from China to cooperate on electrolytic reprocessing, and it has been rebuffed by Japan's CRIEPI due to government policy.

In 2008 IAEA approved an electrorefining laboratory - the Advanced Spent Fuel Conditioning Process Facility (ACPF) at KAERI, which is to be expanded to engineering scale by 2012.  This is envisaged as the first stage of a Korea Advanced Pyroprocessing Facility (KAPF) to start experimentally in 2016 and become a commercial-scale demonstration plant in 2025.

The Russian Institute of Atomic Reactors (RIAR) at Dimitrovgrad has developed at pilot scale pyroprocessing for fast reactor fuel.

Transmutation

Transmutation of one radionuclide into another is achieved by neutron bombardment in a nuclear reactor or accelerator-driven device. In the latter, a high-energy proton beam hitting a heavy metal target produces a shower of neutrons by spallation. The neutrons can cause fission in a subcritical fuel assembly, but unlike a conventional reactor, fission ceases when the accelerator is turned off. The fuel may be uranium, plutonium or thorium, possibly mixed with long-lived wastes from conventional reactors. See also paper on Accelerator-driven Nuclear Energy.

The objective is to change (long-lived) actinides into fission products and long-lived fission products into significantly shorter-lived nuclides. The goal is to have wastes which become radiologically innocuous in only a few hundred years.

Transmutation is mainly by fast neutrons. Since these are more abundant in a fast neutron reactor, such reactors are preferred for transmutation - and of course they can be fuelled with the recovered plutonium. (In a fast reactor americium and neptunium are also fissionable, so can contribute to the energy.) A 2001 BNFL-Cogema study said that full transmutation in a light water reactor would take at least several decades, and recent research has focused on use of fast reactors. Unfortunately the prime contributors to the long-term radiological load in a repository are those which are most difficult to transmute.

Some radiotoxic nuclides, such as Pu-239 and the long-lived fission products Tc-99 and I-129, can be transmuted (fissioned, in the case of Pu-239) with thermal (slow) neutrons. The minor actinides Np, Am and Cm (as well as the higher isotopes of plutonium), all highly radiotoxic, are much more readily destroyed by fissioning in a fast neutron energy spectrum, where they can also contribute to the generation of power.

With repeated recycle in a transmutation system, the radiotoxicity of used nuclear fuel can be reduced to the point that, after a decay period of a few hundred years, it is less radiotoxic than the uranium ore originally used to produce the fuel. The need for a waste repository is certainly not eliminated, but it can be smaller and simpler and the hazard posed by the disposed waste materials is greatly reduced.

DUPIC

Another approach to used nuclear fuel recycling which could be employed by some countries is DUPIC (Direct Use of used PWR fuel in CANDU reactors).

CANDU (CANadian Deuterium Uranium) reactors use as fuel natural uranium which has not undergone enrichment and so could theoretically operate fuelled by the uranium and plutonium that remains in used fuel from light water reactors.

With DUPIC, used LWR fuel assemblies would be dismantled and refabricated into fuel assemblies the right shape for use in a CANDU reactor.  This could be direct, involving only cutting the used LWR fuel rods to CANDU length (about 50 cm), resealing and reengineering into cylindrical bundles suitable for CANDU geometry.

Alternatively, a dry reprocessing technology has been developed which removes only the volatile fission products from the spent LWR fuel mix.  After removal of the cladding, a thermal-mechanical process is used to reduce the used LWR fuel pellet to a powder. This could have more fresh natural uranium added, before being sintered and pressed into CANDU pellets.

The DUPIC technique has certain advantages:

However, as noted above, used nuclear fuel is highly radioactive and generates heat. This high activity means that the DUPIC manufacture process must be carried out remotely behind heavy shielding. While these restrictions make the diversion of fissile materials much more difficult and hence increase security, they also make the manufacture process more complex compared with that for the original PWR fuel, which is barely radioactive before use.

Canada, which developed the CANDU reactor, and South Korea, which hosts four CANDU units as well as many PWRs, have initiated a bilateral joint research program to develop DUPIC and the Korean Atomic Energy Research Institute (KAERI) has been implementing a comprehensive development program since 1992 to demonstrate the DUPIC fuel cycle concept.

Challenges which remain include the development of a technology to produce fuel pellets of the correct high density, the development of remote fabrication equipment and the handling of the used PWR fuel. However, KAERI successfully manufactured DUPIC small fuel elements for irradiation tests inside the HANARO research reactor in April 2000 and fabricated full-size DUPIC elements in February 2001. Atomic Energy of Canada are also able to manufacture DUPIC fuel elements.

Research is also underway on the reactor physics of DUPIC fuel and the impacts on safety systems.

A further complication is the loading of highly radioactive DUPIC fuel into the CANDU reactor. Normal fuel handling systems are designed for the fuel to be hot and highly radioactive only after use, but it is thought that the used fuel path from the reactor to cooling pond could be reversed in order to load DUPIC fuel, and studies of South Korea¹s Wolsong CANDU units indicate that both the front- and rear-loading techniques could be used with some plant modification.

KAERI believe that although it is too early to commercialise the DUPIC fuel cycle, the key technologies are in place for a practical demonstration of the technique.

Main sources:
Madic, C. 2000, Overview of the hydrometallurgical and pyrometallurgical processes for partitioning high-level nuclear wastes, in Actinide and Fission Product Partitioning and Transmutation, Madrid, OECD/NEA.
Laidler, J.J. 2000, Pyrochemical separations technologies envisioned for the US accelerator transmutation waste system, OECD/NEA workshop proceedings: Pyrochemical Separations; - also personal communication.
NuclearFuel 15/10/01 & 31/1/05.
American Nuclear Society Nuclear News Sept 2005, statement Nov 2005.
Park, J.J. et al, 2000,Technology and implementation of the DUPIC concept for spent nuclear fuel in the ROK
Yang, S.Y et al, 2006, The status and prospect of DUPIC fuel technology, Nuclear Engineering and Technology, Vol.38, 4.
McFarlane, H.F. 2004, Nuclear Fuel Reprocessing, in Encyclopedia of Energy, Elsevier.
Wood, Janet 2006, Should USA Reprocess? Nuclear Engineering Int'l Sept 2006.
OECD/NEA 2007, Management of Recyclable Fissile and Fertile Materials, NEA # 6107.

UK Nuclear Decommissioning Authority, 2007, Uranium and Plutonium: Macro-economic Study.

IAEA 2007, Management of Reprocessed Uranium - current status and future prospects, Tecdoc 1529.

GEH personnel

 





DPRK Flag North Korea Special Collection


http://cns.miis.edu/research/korea/repro.htm


Factsheet on North Korean Nuclear Reprocessing Statement

Updated April 23, 2003


On 18 April 2003, the Korean Central News Agency (KCNA), the official North Korean news agency, published a statement by a Foreign Ministry spokesperson about the recently announced Beijing talks. According to KCNA’s English translation, the North Korean spokesman declared that North Korea was “successfully reprocessing more than 8,000 spent fuel rods at the final phase as we sent interim information to the U.S. and other countries concerned early in March after resuming our nuclear activities from December last year.” Several Western media sources have reported this statement as an official declaration that North Korea has started to reprocess its 8,000 spent fuel rods. However, a close look at the original Korean text shows that KCNA provided an inaccurate English translation of the original statement. The Korean-language text should be translated as “We are successfully making progress in the last stages towards the task of reprocessing the approximately 8,000 spent fuel rods.” The Korean text implies progress is being made in the final stages necessary to begin reprocessing, but does not specify what tasks remain to be completed before plutonium can be separated from the spent fuel rods. This text is somewhat ambiguous, but is definitely not a straightforward declaration that reprocessing has started [which would be phrased differently in Korean]. After the Foreign Ministry statement was released, a U.S. official told Reuters the United States had “no information to indicate that North Korea has begun reprocessing.”

Given the controversy over the different implications between the Korean and English versions of the Foreign Ministry statement, KCNA issued a corrected version of the English translation on April 21st. It corrected the original translation to read “We are successfully going forward to reprocess work of more than 8,000 spent fuel rods at the final phase...” South Korea’s Yonhap News Agency reported that a KCNA employee claimed to have made the correction based on his personal judgment in order to better reflect the original Korean text in the English translation. He stated that the corrected translation was made without any instruction from or discussion with the North Korean government. Despite the correction, the statement still remains ambiguous.

The North Korean statement was the first official comment by the Democratic People’s Republic of Korea (DPRK) about the upcoming trilateral meetings between the United States, North Korea and China that began in Beijing on April 23rd. According to the North Korean Foreign Ministry spokesperson, the Chinese government’s role was solely as host and “the essential issues related to the settlement of the nuclear issue will be discussed between the DPRK and the U.S.” Despite this rhetoric, the inclusion of a third party is a concession by North Korea, which had previously demanded bilateral talks with Washington. The Bush administration had also made a significant concession in agreeing to limit the talks to three parties, instead of the multilateral talks including Japan and South Korea that Washington had originally demanded. Despite being excluded from this initial round of talks, both the South Korean and Japanese governments have come out in favor of the meetings. The Bush administration has given clear indications that Washington expects both Seoul and Tokyo to take an active part in future rounds of discussions.

Original English text of the DPRK statement issued by the Korean Central News Agency (KCNA), 18 April 2003

“The DPRK-U.S. talks for the settlement of the nuclear issue on the Korean peninsula is slated to open in Beijing shortly. At the talks the Chinese side will play a relevant role as the host state and the essential issues related to the settlement of the nuclear issue will be discussed between the DPRK and the U.S.

There is a wide range of international opinion on the Beijing talks as they are to open at a time when the Iraqi war was fought.

The Iraqi war teaches a lesson that in order to prevent a war and defend the security of a country and the sovereignty of a nation it is necessary to have a powerful physical deterrent force only.

As we have already declared, we are successfully reprocessing more than 8,000 spent fuel rods at the final phase, as we sent interim information to the U.S. and other countries concerned early in March after resuming our nuclear activities from December last year.

We have already clarified our stand that if the U.S. has a willingness to make a bold switchover in its Korea policy, we will not stick to any particular dialogue format, and we would like to confirm the U.S. intention in the forthcoming talks.”

Corrected version of paragraph 4 of the original translation, as of 21 April 2003

As we have already declared, we are successfully going forward to reprocess work of more than 8,000 spent fuel rods at the final phase as we sent interim information to the U.S. and other countries concerned early in March after resuming our nuclear activities from December last year.

Questions and Answers about the North Korean statement

1) Does this statement give any firm indications about North Korea’s nuclear intentions?
The timing of the statement suggests that North Korea is trying to develop additional leverage prior to the start of talks with the United States next week. By announcing its readiness to begin reprocessing—but not actually starting to reprocess—North Korea is signaling the United States that if negotiations do not produce an acceptable deal, it can proceed quickly to produce additional plutonium that could be used in nuclear weapons. This brinksmanship is consistent with past North Korea negotiating tactics, such as North Korea’s 1993 announcement of its intention to withdraw from the Nuclear Nonproliferation Treaty (which was ultimately suspended one day before it took effect).

An alternative interpretation is that North Korea may attempt to use its willingness to negotiate with the United States as cover for beginning to reprocess its 8,000 spent fuel rods. By indicating a willingness to resolve the crisis through negotiations, North Korea could try to defuse the international reaction to reprocessing and reduce the chance of a U.S. pre-emptive strike against North Korean nuclear facilities.

2) Would the United States know if North Korea actually started reprocessing?
Yes. There are two major signatures for reprocessing. The first is the emission of krypton-85 (Kr-85), a radioactive gas, from a reprocessing facility. The second is thermal signatures emanating from the facility. Both signatures can be detected remotely. Kr-85 can be detected by air sampling relatively far from the site, and the thermal signature can be detected by infrared sensors on satellites. The United States is capable of using both methods. U.S. government officials have expressed confidence that North Korean reprocessing would be detected quickly. However, no signatures have been detected to date that would indicate actual reprocessing has started.

3) If North Korea decided to begin reprocessing, how much plutonium could they produce and how quickly could they produce it?
U.S. intelligence officials claim that North Korea already possesses enough fissile material for one to two nuclear weapons. This material came from plutonium extracted from spent fuel rods removed from the 5MW(e) Experimental reactor in 1989. Both China and Russia have expressed doubts that the DPRK has the technical capacity to construct a working nuclear warhead. North Korea has not tested nuclear weapons, although there are indications that they successfully completed high explosive tests necessary for triggering a nuclear weapon. North Korea’s nuclear program appears to be capable of at least developing a small nuclear arsenal. The most immediate concern, as evident from the North Korean statement, is the 8,000 spent-fuel rods still held in storage at the Yongbyon nuclear complex. If these spent-fuel rods were to be reprocessed, Pyongyang would have enough plutonium for approximately five nuclear weapons, and the process would only take a few months once reprocessing began. In the medium-term, the 5MW(e) Experimental Reactor could also produce enough plutonium for approximately one nuclear device per year. North Korea’s capacity could be further expanded with the addition of the currently unfinished 50MW(e) reactor in Yongbyon-kun and a 200MW(e) reactor in T’aech’on-kun. These facilities could be operational within five years and together have the potential to produce enough plutonium for 35 to 50 bombs annually.

Although less developed than the plutonium program, North Korea’s HEU program may be capable of producing enough fissile material to construct six bombs annually within the next few years. Unlike plutonium facilities, HEU facilities are difficult to detect. It is unclear how far the North Korean HEU program has progressed. However, a CIA estimate from late 2002 claimed that North Korea might have a gas-centrifuge enrichment facility within three years. If that estimate is accurate, a North Korean HEU program could produce enough fissile material for six weapons per year starting in 2006. (See North Korea's Nuclear Program: Key Concerns, http://cns.miis.edu/research/korea/index.htm.)

4) If North Korea begins reprocessing, how will the United States respond?
The United States has not publicly stated how it would respond if North Korea began reprocessing. However, the United States is widely believed to have privately warned North Korea not to take this step. Possible U.S. responses might include withdrawing from further talks, efforts to get the United Nations Security Council to authorize sanctions against North Korea, or a pre-emptive strike against North Korean nuclear facilities. (See Military Options for Dealing with North Korea's Nuclear Program, http://cns.miis.edu/research/korea/dprkmil.htm.)

5) What implications will the North Korean statement have for the scheduled talks?
The statement suggests that North Korea will adopt a tough negotiating position in the talks and is not intimidated enough to make major concessions without getting anything in return. North Korea is also signaling its willingness to move forward with reprocessing if the United States proves unwilling to negotiate an acceptable deal.

The impact will also depend on how the Bush administration reacts. If the Bush administration was seeking an excuse to back away from the talks, the North Korean statement did provide one. However, the United States could instead respond by demanding that North Korea not reprocess its spent fuel as a condition for U.S. participation in the talks. One option could be for China—the third party in the talks—to send personnel to the North Korean nuclear facilities to verify that reprocessing has not begun. In exchange, the United States could agree to forego any military options while North Korea is negotiating in good faith.

6) What impact will the North Korean statement have on U.S. policy toward the nuclear crisis?
The statement likely confirmed the views of many Bush administration officials that North Korea will be a difficult negotiating partner that cannot be trusted to live up to its agreements. This will increase U.S. demands for iron-clad verification clauses in any agreement.

More broadly, there are two key unresolved questions about the negotiations. Is North Korea willing to give up its current and potential nuclear weapons capability in a visible, verifiable, and irreversible way? If so, what is the United States willing to give North Korea in return? The answers to these questions will ultimately determine whether a diplomatic settlement of the crisis is possible.


This factsheet was prepared by Phillip C. Saunders, Daniel A. Pinkston, Stephanie Lieggi, Mari Sudo, and Charles Ferguson of the Center for Nonproliferation Studies, Monterey Institute of International Studies.

List of CNS Experts on the DPRK


Return to the North Korea Special Collection.














http://whyfiles.org/275nukewaste/index.php

Nuclear fuel reprocessing: A cure that’s worse than the disease?

POSTED 28 FEBRUARY 2008


Nuclear power's future: Reprocessing returns?
First nuclear fission experiment 1934 Nuclear electricity 'too cheap to meter' 1954 First civilian reactor in U.S. opens 1957 India tests nuclear bomb built from reprocessed waste 1974 Three Mile Island (Penn.) plant melts down 1979 Nuclear Waste Policy Act plans 1 repository in east, 1 in west, 1982 Congress: build Yucca Mountain, Nevada; ditch eastern dump 1987 Chernobyl (Ukraine) melts down 1986 Last nuclear plant on line in United States 1996 Planned startup date for Yucca Mountain 1998 Today's date 2008 Current estimated startup at Yucca Mountain 2018? Yucca Mountain full, second dump needed 2030?Is nuclear back? The growing energy shortage, combined with the fact of greenhouse warming, have sparked a flurry of interest in non-carbon energy sources, including nuclear energy. After all, according to the Nuclear Energy Institute, nuclear is "Clean air energy."

The result is a sudden end to a 30-year drought in U.S. nuclear-plant applications. By February, 2008, the U.S. Nuclear Regulatory Commission (NRC) has received applications for six new reactors.

The long drought had several causes. Cost was one -- the last U.S. nuclear plants came in way late and way over budget, partly due to safety and regulatory changes following the 1979 meltdown at Three Mile Island. "One reason you saw the stall in nuclear building was that the uncertainty made investors much more cautious about getting involved," says Todd Allen, an assistant professor of nuclear engineering at the University of Wisconsin-Madison. "There was a lack of certainty from the time of taking out a loan to selling electricity." Regulatory delays and design changes can eat up profits on such an expensive plant, he adds.

Reactor operators are now trying to control costs by standardizing their designs, and the NRC has promised faster regulatory decisions. Nuclear power makes about 20 percent of U.S. electricity, and about 16 percent globally.

But we see little cause for optimism about a second key source of the nuclear willies -- safe disposal of the intensely radioactive spent fuel that must be removed from reactors. The giant, federal nuclear-waste warehouse at Yucca Mountain, Nev. was supposed to solve the spent-fuel problem. But Yucca was scheduled to open 10 years ago, and it is unlikely to open for another 10 years -- if ever.

shaes made up of red and white balls collide and split off
When a neutron hits a uranium-235 atom and causes it to split ("fission") in a nuclear reactor, we get fission products and "transuranics" (heavy elements like plutonium), along with more neutrons and a gob of energy.

With Yucca in limbo (some scientists say it cannot contain radwaste for 1 million years), the high-level waste problem remains unsolved.

So in the year that Yucca was supposed to celebrate its 10th birthday, here's our question: Who's got some good ideas for safely storing high-level nuclear waste?

Two men stand among six small off-white silos enclosed by barbed wire
These "dry casks" are an increasingly popular, but temporary, solution to radioactive waste storage at reactor sites. Photo: NRC

Radwaste: The original Mr. Yuck
High-level radwaste -- the yuck Yucca is slated to receive -- is spent fuel from nuclear reactors, and it's roughly one million times more radioactive than fresh uranium fuel. High-level waste is extremely carcinogenic, even lethal, and must be handled by remote control or under heavy shielding.

Spent fuel can also provide the basis for good ol' explosive nuclear bombs and dirty bombs (which spew radiation without that familiar mushroom cloud). So to prevent nuclear proliferation, nuclear terrorism, and a cancer epidemic, spent fuel must be contained virtually forever.

The goal at Yucca is to safely store 70,000 tons of radwaste for 1 million years. Over those 10,000 centuries, the radioactive isotopes will gradually cool and be converted into stable, non-radioactive isotopes. (Isotopes are versions of an element with a different number of neutrons. Different isotopes decay at different rates; with many elements, some isotopes are stable, others will decay and release radiation.)

For the repository at Yucca, about 100 miles northwest of Las Vegas, the U.S. Department of Energy (DOE) would love to follow GambleVille's marketing mantra ("What radiates near Vegas stays near Vegas"). Tall smokestack sends billowing puffs of white gas clouds into the airBut the giant repository is unlikely to open for at least another 10 years, and in the meantime, spent fuel will continue stacking up at reactors across the country, making a splendid target for terrorists eager to release a deadly cloud of radiation or even trigger a nuclear meltdown.

As electric generating plants spew out millions of tons of the greenhouse gas carbon dioxide, interest in nuclear energy is rising. But new plans to reprocess nuclear fuel have raised old fears. Photo ©David Tenenbaum

Reprocessing redux?
The slipping schedule at Yucca has refocused attention on nuclear fuel reprocessing. When uranium fuel is first used in a reactor, it releases only about 1 percent of its nuclear energy (the fuel must then be replaced because a buildup of uranium breakdown products interferes with the chain reaction).

Unfortunately, many of these "fission products," such as cesium 137 and strontium 90, are remarkably radioactive. Still, about 99 percent of the nuclear energy remains in the spent fuel, mainly in the uranium 235 and plutonium 239. During reprocessing, these isotopes are separated out and blended into new fuel rods that go into another reactor. The fission products, however, become high-level radwaste.

Recycling uranium makes more sense than one-time use to many experts, including radiochemist Peter Burns of Notre Dame University. "Why are we calling this stuff waste? Why do we have a policy of sending this stuff to a nuclear waste repository?"




















Reframing reprocessing: Miracle of recycling, or nightmare of proliferation?
Long before Americans were setting their bottles and cans on the curb for recycling, nuclear folks were thinking about recycling nuclear fuel. Recycling, AKA "reprocessing," can

Reduce the radioactivity and/or mass of spent fuel;

Produce more energy from each ton of uranium mined; and

"Close the fuel cycle" by reducing environmental impacts during fuel production and disposal.

Long line of angry protestors shout and hold signs written in Asian charactersProtestors from Greenpeace demonstrate in a blizzard at the gates of the new Japanese reprocessing plant, in 2004. Photo by J. Sutton-Hibbert, Greenpeace

At least, that's the theory. The reality of reprocessing is more contested than the seventh game of a Yankee-Red Sox World Series, and the process is a bit more complicated than melting aluminum cans into new cans for Cherry Toothrot TM. Yet while reprocessing is controversial in the United States, it's common in France, the United Kingdom, Russia and now Japan.

Here's our quickie reprocessing primer: Robots chop up the hot, highly radioactive fuel rods, dissolve the chunks in acid, and separate the plutonium and uranium from the fission products (which block chain reactions). The uranium and plutonium are then blended into new fuel.

Wide and low blue trucks move massive tanks of waste down the highway
Road transport of spent fuel in Japan. Photo: World Nuclear Transport Institute

Rejuvenating reprocessing
Thirty years after the United States rejected reprocessing of civilian nuclear waste, the DOE is reinvestigating reprocessing through the Global Nuclear Energy Partnership, initiated in 2006. GNEP offered this deal to other nations: If you want to use nuclear electricity, the United States will supply the fuel -- if you promise to send your waste back to trusty Uncle Sam for reprocessing. Twenty-one nations have signed on to that program, which also intends to design smaller, safer reactors for developing countries.

Critics charged that GNEP's emphasis on reprocessing marked a dangerous and expensive policy about-face. GNEP "undermines U.S. nonproliferation policy, would cost taxpayers $100 billion or more, and ... [would] not solve the nuclear waste problem," wrote the Union of Concerned Scientists and 39 other groups last fall.

Also last fall, a National Research Council report recommended rejecting GNEP's reprocessing research regime, although it did favor more restricted research on recycling. (The original GNEP proposal had included generous funding to build GNEP's infrastructure, but Congress scotched that part.)

A black, solid crust of toxic chemicals coats inside of dank tank
Massive tanks of liquid nuclear waste remain at the Hanford Site in Washington State after decades of reprocessing to extract plutonium for nuclear weapons from reactor fuel. Pacific Northwest National Laboratory and others are working to remediate this waste, but for chemical and radiological reasons, it's tough slogging. Although the photo shows the inside of a double-walled tank, some early tanks have only one wall and pose little barrier to the spread of radiation. Hanford is on the banks of the Columbia River. Photo: PNL

Reenergizing reprocessing
Gregory Choppin, a professor of chemistry at Florida State University who has a long acquaintance with radiation chemistry says efficiency is a key argument for reprocessing, which extracts more energy from the uranium fuel, and therefore reduces the need to mine uranium. "If we go into reprocessing to recover the 99.5 percent of unburned uranium, and recycle it, we would not have to do any more uranium mining for 400 years," says Choppin. "That would be a tremendous advantage because uranium mining is very dangerous," especially in terms of lung disease, including cancer.

The coming nuclear boom has skyrocketed the price of uranium, but the Navajo Nation is still reeling from the last uranium boom, says Doug Brugge, associate professor of public health at Tufts University. Brugge says the "federal government has given compensation to over 6,000 uranium miners, millers and other workers" who suffered lung disease. "The government obviously has pretty stringent standards for compensation, so that's probably a low estimate, but ... that's a lot of people who died, or were made ill enough to qualify." In 2005, the Navajo Nation banned uranium mining, Brugge adds. "Their experience with uranium was so devastating that it overwhelms any financial incentives."

But could reprocessing also reduce the burden of finding safe storage for spent fuel? Yes, says Choppin. "You take out the plutonium, uranium, and probably some neptunium, which decays into plutonium, and keep them aside for further burning... so you not only destroy the plutonium and uranium 235, but you also get a lot of energy out."

However, the extent of reduction is open to debate. According to Michael Corradini, a professor of engineering physics at the University of Wisconsin-Madison, "You don't reduce the radioactivity that goes into the ground, you do reduce the volume, so ... you still have to dispose of the radioactive waste that was caused by the fission. That solid, compact material still has to be buried."

 Large drill head points toward the ceiling of an underground mine
Drilling at the McArthur River uranium mine in Canada. Uranium can decay into the gas radon, which causes lung cancer in uranium miners. Photo: Cameco

Dig this crazy process?
Reprocessing would be a mixed benefit, says John Ahearn, a former chairman of the Nuclear Regulatory Commission and director emeritus of Sigma Xi, the scientific research society. "It's not a permanent solution, does not reduce the heat load at all, because it does not get rid of the real heat-generating material [the fast-decaying fission products]. It does reduce the volume and mass, because you have pulled out the uranium, which is a large contribution, and the plutonium, which is one of the problems."

Ahearn adds that the viability of reprocessing depends "on whether you can separate all the actinides [the heavy elements, including uranium and plutonium], and can re-burn them. These are all technology issues that not been resolved."

Ahearn says reprocessing could reduce the needed volume of the repository by 30 percent, which "would go a long way toward resolving the issue of whether there is enough space in Yucca Mountain." Still, he says the technical questions about reprocessing would need 10 to 20 years of further study, so even if reprocessing proves helpful, it will not help in the short term.

Two scientists  hunker down among small river rocks, drilling into soil
Pacific Northwest National Laboratory staff collect groundwater samples, looking for radiation leaks from Hanford's giant "tank farm" holding reprocessing waste from the nuclear-bomb biz. Photo: Pacific Northwest National Laboratory.

Reprehensible reprocessing?
Some observers take a much dimmer view of reprocessing, just as they did when the issue last surfaced 30 years ago. Reprocessing is "an incredibly complicated process, and it creates a liquid high-level waste stream," says Brice Smith, an assistant professor of physics at the State University of New York at Cortland.

Liquids are inherently tougher to contain than solids, and he says these wastes would need to be cast into glass or ceramic logs before going to underground storage. That process "has proven to be a significant challenge" at federal nuclear sites in Washington State, Idaho and South Carolina, he adds. "This liquid reprocessing waste would be very similar in a lot of respects to what we had left over from nuclear weapons, and it's very expensive" to handle.

Crane towers a large tank during building, dozens of workers seen walking on site, small in comparison. Hanford has 177 radioactive waste storage tanks, built from 1943 to 1985, with a capacity ranging up to 1.1 million gallons. These are double-shell tanks, a safety innovation introduced in 1968. Photo: PNL

Reprocessing of military waste does have a nasty environmental history: Huge tanks of radwaste at federal nuclear sites have awaited safe disposal for as much as half a century. According to Robert Alvarez, a nuclear policy specialist at the Institute of Policy Studies, less than 1 percent of defense reprocessing wastes have been stabilized, despite the spending of billions of dollars on the effort in Washington State and South Carolina. The rest remains in tanks with varying degrees of integrity.

Rejecting reprocessing
Alvarez, who was a senior policy advisor in the DOE from 1993 to 1999, says GNEP is unlikely to survive scrutiny. "All this was flying around at the level of magical thinking, because no-one has taken a hard look" at the implications. For example, GNEP proposed to remove the fission products strontium and cesium from the spent fuel, Alvarez says. "No one has done this before, the amount of radioactivity is breathtaking; it's billions of curies. This is fantastically hot." (One curie of radioactive material emits the same radiation as one gram of radium 226: 37 billion radioactive disintegrations per second.)

This waste would need to be stored above ground for 100 years, before being diluted and placed in underground storage.

Even if, as GNEP plans, only 1 percent of elements heavier than uranium (including plutonium, americium and curium) end up in the waste, Alvarez sees danger. "That turns out to be many times more curies than was generated by the nuclear arms race."

Overall, GNEP seems rather helter-skelter, Alvarez charges. "These guys did not have any kind of plan, no estimate of the waste volume, concentration, how to manage it, dispose of it, and how much it is all going to cost."

But reprocessing is a big lure for federal nuclear labs and some in Congress, Alvarez says. "Politicians keep drinking the Kool Aid of recycling ...without understanding that this is the same thing we had to deal with 30 years ago" when India got the bomb through reprocessing. Reprocessing "is not recycling. It is a gateway technology for the manufacture of nuclear weapons, and it generates a large amount of waste which will make the [waste] problem worse."

As Alvarez indicates, during reprocessing, plutonium is separated from spent fuel, and it can then become a primary fuel for nuclear weapons. The military reactors built during and after World War II were designed to make plutonium for fission (atomic) and fusion (hydrogen) bombs.

When civilian nuclear power arrived in the 1950s, reprocessing was suggested as a way to stretch the uranium supply. Then in 1974, India tested a nuclear bomb made from reprocessed research-reactor fuel, and Presidents Ford and Carter rejected reprocessing in the civilian nuclear realm.

Preventing proliferation
Although opponents warn that reprocessing does the dangerous plutonium separation for nuclear terrorists and states that want the bomb, observers are not unanimous about the dangers of reprocessing. GNEP, for example, has proposed to find a technical solution that would block proliferation during reprocessing. One option is to leave high-intensity isotopes in the newly made fuel, to make it literally "too hot to handle." "Reprocessing is more of a proliferation risk than direct disposal," concedes Ahearn, but he thinks it possible to safeguard a reprocessing plant against proliferation. "There are reprocessing plants in Europe that have operated for decades, Japan is about to open a huge new one. I don't know any case where the plutonium from any of those plants has been stolen."

Choppin says enhanced international cooperation could address proliferation concerns. "The IAEA [International Atomic Energy Agency] already does a lot of international inspection of nuclear energy processes. If the IAEA is allowed to supervise, monitor the reprocessing, they could keep track of proliferation."

Train chugs down tracks hauling two large white tanks among its cargo.
A train used for transporting radioactive materials in the United Kingdom. Transport containers must resist fires, accidents and terrorists. Photo: WNTI

Choppin says anti-proliferation efforts may benefit from a reorganization of the nuclear infrastructure. "I like a proposal by South Africa to build four or five reactors around a reprocessing plant" and reduce vulnerable shipments of nuclear material. "This has been suggested in Europe, to localize the reactors, so ... all the dangerous stuff is right there, it's easy to put the safeguards on and secure" the plutonium.









Basket of waste questions
For 30 years, as some nations reprocessed their spent nuclear fuel, the U.S. nuclear-waste strategy focused on a "geologic repository;" an underground wastebasket designed to prevent proliferation and environmental contamination for up to 1 million years.

Brown and desolate overview of Yucca Mountain and surrounding lands.
Aerial view of Yucca Mountain, Nev., site of national repository. Photo: Nuclear Energy Institute

In 1987, Congress chose Nevada for a single national storehouse for spent civilian fuel, even though the 1982 Nuclear Waste Policy Act had called for a second repository in the eastern United States. Yucca was supposed to start accepting spent fuel rods in 1998, but hasn't yet, and the schedule continues to slip. Indeed, by the time Yucca does open (the optimistic predictions say in 2018), the national spent-fuel stockpile will already exceed Yucca's design capacity of 70,000 tons.

In other words, a second waste site will be needed even before the first one opens its doors. But beyond civilian spent fuel, the overall radwaste problem also includes low-level waste and an ocean of high-level liquid waste left over from making 30,000+ nuclear bombs.

Nuclear waste -- spent fuel generated per year
Graph compares current and projected levels of nuclear waste production across the globe, North America leads the pack by far.
Spent fuel is not just a problem in the United States. Europe is also struggling with the problem. Graph by Emmanuelle Bournay, UNEnvironment Program

Mountain of trouble
About $9-billion into the Yucca project, the storage site remains the focus of a labyrinth of technical, economic and political questions. Here's a small sample:

Technical: Can Yucca contain the radiation? How long before the cans holding the waste start to leak, and how soon will the radiation reach the environment?

Economic: Nuclear utilities (and their customers) have already paid the Department of Energy $27 billion to finance the Nevada dump, which was supposed to start taking waste in 1998. The utilities have begun winning lawsuits, claiming that they are paying to store waste that is now the fed's responsibility. These suits could eventually cost the feds double-digit billions (see #1 in the bibliography).

Political: Plenty of Silver Staters resent having a dump dumped on what was a weak, under-populated state, in a location already despoiled by nuclear explosions at the Nevada test site, site of Yucca Mountain. One vocal local, Harry Reid, happens to be Senate Majority Leader.

Can the canisters contain?
A lot of thought and expense has gone into designing the canisters that will hold waste at Yucca, but "eventually they will breach," says radiochemist Burns of Notre Dame. "The canisters are certain to fail, it's only a matter of how long. In 100 years? No. Maybe in 1,000. It's pretty much certain at 10,000 or 100,000 years." An earthquake, volcanic activity or a human intrusion could throw the release schedule out the window, he adds.

Yucca was chosen because it's remote and dry, but studies have found that it has an oxidizing environment, Burns says. "The big problem is that as soon as the canisters breach, the fuel starts to oxidize and release radioactivity in the groundwater. The bottom line is that no geologic environment is so sufficiently stable, and no canister design so robust, that you would expect it to last forever."

Textured map of Utah, small, square section near California border is highlighted in green.
Yucca Mountain, where a radwaste repository is under construction, is inside the National Test Site, where about 1,000 atomic bombs were tested between 1951 and 1992. Graphic: Nuclear Energy Institute

These thoughts lead Burns to favor matching waste and repository for maximum stability. "Imagine we adopt reprocessing, and create two or three types of waste forms [such as glass or zeolite] to handle waste that can't be recycled," then build several geological repositories with chemical conditions suited to each type of waste. "We would get the best waste form for the environment," Burns says. "Yucca would be great for borosilicate [glass], but not for spent fuel. I imagine deep granite, an anoxic, reducing environment, would be great. The nuclear fuel would be an order of magnitude more stable, less soluble."

That approach might work in the long run, but waste continues to pile up in the short run. Each civilian nuclear power reactor in the United States has a giant swimming pool full of hot fuel rods -- and many reactor operators have already exceeded their original design capacity. These pools could be an irresistible draw to terrorists, who might be able to start a radiation-spewing fire by draining the pool or shutting off the cooling-water pump.

Deep, glowing and otherworldly pool of water surrounds barrels full of toxic waste
The interim storage pool at the French reprocessing plant, which opened in 1990. Photo: Areva

Waste not, want not?
This year, as the Department of Energy prepares to finally apply for a license for its Yucca dump, fuel that can't fit the overloaded swimming pools at nuclear reactors is being moved to "dry casks," air-cooled steel containers that require monitoring and protection against wackos, but need neither the water nor the pumps used in cooling ponds.

Dry casks are "now clearly the method of choice," says Ahearn, the former nuclear regulator. "To build another swimming pool for a reactor is a whole messy licensing process, and companies have realized that dry casks are safe and economical; that's the trend."

Some skeptics who question whether Yucca Mountain can or should be opened say that consolidating the casks would make them easier to guard. A 50- to 100-year cooling-off period would allow the development of better waste-disposal technology.

Chart shows ten nations and levels of nuclear power use-the US leads by a lot
Nuclear Energy Institute

While we've highlighted a thorny dispute about the wisdom of reprocessing, our experts were unanimous on this: With or without reprocessing, geologic storage will always be needed for high-level radioactive waste that must be isolated indefinitely from the environment and sociopaths.

Rather than fading away, the need for radwaste storage grows more acute. In the United States, an estimated 55,000 tons of civilian spent fuel await entombment, and 103 operating reactors are producing another 2,000 tons of spent fuel each year.

Graph shows heavy building of nuclear reactors in early 70s, demonstrates comparatively little growth of industry today
Reactor construction peaked during the 1970s, but a resurgence is now under way around the world -- including the United States. Graph by Philippe Rekacewicz, UNEP/GRID-Arenda, UNEnvironment Program

While the United States awaits applications for more new reactors, the international picture shows rapid growth, according to Germany's Der Spiegel: "Currently there are 435 atomic reactors generating electricity in 31 countries across the globe. They fill 6.5 percent of the world's total energy demand and use close to 70,000 tons of enriched uranium per year [about one Yucca Mountain worth of waste per year, in other words] ... At present, 29 nuclear power plants are under construction and there are concrete plans to build another 64. Another 158 are under consideration" (see #2 in the bibliography).


















Reprocessing -- no silver bullet
Although reprocessing remains highly controversial, our experts agreed that at some point, radioactive material that can supply no further energy will need burial to deter proliferation and environmental contamination. "Even if you do reprocessing, you still end up with some waste," says Ahearn.

In France, and in the other countries that are reprocessing, "They cycle back the long-lived material, but still have to bury something," says nuclear engineer Michael Corradini. "The French are reprocessing, taking 99 percent of the mass and putting it back into plants to reuse the uranium, burn down the plutonium, but they are still building up more waste -- you can change the nature of it, but you can't get rid of it."

Recycling builds up a waste stream containing short-lived (and intensely radioactive) isotopes like strontium 90 and cesium 137, while making electricity from the long-lived isotopes of plutonium and other transuranics, Corradini adds. "My message is that you always have to bury something... There is no magic bullet. Eventually you will have a radioactive substance which has various times in which it decays, and you will have to put it in geological isolation."



http://www.fpif.org/fpiftxt/5351

Nuclear Recycling Fails the Test

Robert Alvarez | July 7, 2008

Editor: Miriam Pemberton

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Foreign Policy In Focus

Over the past few years, attention to the recycling of nuclear power spent fuel has grown. Fears of global warming due to fossil fuel burning have given nuclear energy a boost; over the next 15 years dozens of new power reactors are planned world-wide. To promote nuclear energy, the Bush administration is seeking to establish international spent nuclear fuel recycling centers that are supposed to reduce wastes, recycle uranium, and convert nuclear explosive materials, such as plutonium to less troublesome elements in advanced power reactors.

Advocates, such the Heritage Foundation, a conservative think-tank, argue that used fuel at U.S. power plants contain enough energyto power every U.S. household for 12 years.” Heritage points out that nuclear recycling “can be affordable and is technologically feasible. The French are proving that on a daily basis. The question is: Why can't oui?”

The key to recycling is being able to reuse materials while reducing pollution, saving money and making the earth a safer place. On all accounts, nuclear recycling fails the test.

Nuclear Recycling and the Environment

In order to recycle uranium and plutonium in power plants, spent fuel has to be treated to chemically separate these elements from other highly radioactive byproducts. As it chops and dissolves used fuel rods, a reprocessing plant releases about 15 thousand times more radioactivity into the environment than nuclear power reactors and generates several dangerous waste streams. If placed in a crowded area, a few grams of waste would deliver lethal radiation doses in a matter of seconds. They also pose enduring threats to the human environment for tens of thousands of years.

Compairson of RadioactivityIn Europe reprocessing has created higher risks and has spread radioactive wastes across international borders. Radiation doses to people living near the Sellefield reprocessing facility in England were found to be 10 times higher than for the general population. Denmark, Norway, and Ireland have sought to close the French and English plants because of their radiological impacts. Discharges of Iodine 129, for example, a very long-lived carcinogen, have contaminated the shores of Denmark and Norway at levels 1000 times higher than nuclear weapons fallout. Health studies indicate that significant excess childhood cancers have occurred near French and English reprocessing plants Experts have not ruled out radiation as a possible cause, despite intense pressure from the nuclear industry to do so.

Nuclear recycling in the U.S. has created in one of the largest environmental legacies in the world. Between the 1940’s and the late 1980’s, the Department of Energy (DOE) and its predecessors reprocessed tens of thousands of tons of spent fuel in order to reuse uranium and make plutonium for nuclear weapons.

By the end the Cold War about 100 million gallons of high-level radioactive wastes were left in aging tanks that are larger than most state capitol domes. More than a third of some 200 tanks have leaked and threaten water supplies such as the Columbia River. The nation’s experience with this mess should serve as a cautionary warning. According to DOE, treatment and disposal will cost more than $100 billion; and after 26 years of trying, the Energy Department has processed less than one percent of the radioactivity in these wastes for disposal. By comparison, the amount of wastes from spent power reactor fuel recycling in the U.S. would dwarf that of the nuclear weapons program generating about 25 times more radioactivity.

The “Once Through” and “Closed” Nuclear Fuel Cycles

For 30 years the U.S. has refrained from reprocessing commercial spent power reactor fuel to use plutonium in power plants. Instead intact spent fuel rods were to be sent directly to a repository a “once through” nuclear fuel cycle. Radioactive materials in spent fuel are bound up in ceramic pellets and are encased in durable metal cladding, planned for disposal deep underground in thick shielded casks.

Although the U.S. continued to reprocess spent fuel from military reactors, the “once through” fuel cycle was adopted by President Carter in 1977 for commercial nuclear power. Three years earlier, India had exploded a nuclear weapon using plutonium separated from power reactor spent fuel at a reprocessing facility. President Ford responded in 1976 by suspending reprocessing in the United States. President Carter converted the suspension into a ban, while issuing a strong international policy statement against establishing plutonium as fuel in global commerce. President Carter’s decision reversed some 20 years of active promotion by DOE’s predecessor, the U.S. Atomic Energy Commission (AEC), of the “closed” nuclear fuel cycle. The AEC had spent billions of dollars in an attempt to commercialize reprocessing technology to recycle uranium and provide plutonium fuel for use in “fast” nuclear power reactors.

Global Uranium RecyclingRecycling advocates are seeking to overturn this long-standing policy and point to a new generation of “fast” reactors to breakdown plutonium so it can’t be used in weapons. Since the 1940’s, it was understood that “fast” reactors generate more subatomic particles, known as neutrons, than conventional power plants and it is neutrons which split uranium atoms to produce energy in conventional reactors. The U.S. actively promoted plutonium-fueled fast reactors for decades because of the potential abundance of neutrons, declaring that they held the promise of producing electricity and making up to 30 percent more plutonium than they consumed.

With design changes, fast reactors are, ironically, being touted in the U.S. as a means to get rid of plutonium. However, the experience with “fast reactors” over the past 50 years is laced with failure. At least 15 “fast” reactors have been closed due to costs and accidents in the U.S., France, Germany, England, and Japan. There have been two fast reactor fuel meltdowns in the United States including a mishap near Detroit in the 1960’s. Russia operates the remaining fast reactor, but it has experienced 15 serious fires in 23 years.

Plutonium makes up about 1 percent of spent nuclear fuel and is a powerful nuclear explosive, requiring extraordinary safeguards and security to prevent theft and diversion. It took about 6 kilograms to fuel the atomic bomb that devastated Nagasaki in 1945. Unlike plutonium bound up in highly radioactive spent nuclear fuel, separated plutonium does not have a significant radiation barrier to prevent theft and bomb making, especially by terrorists.

Plutonium is currently used in a limited fashion in nuclear energy plants by being blended with uranium. Known as mixed oxide fuel (MOX), it can only be recycled once or twice in a commercial nuclear power plant because of the buildup of radioactive contaminants. According to a report to the French government in 2000, the use of plutonium in existing reactors doubles the cost of disposal.

The unsuccessful history of fast reactors has created a plutonium legacy of major proportions. Of the 370 metric tons of plutonium extracted from power reactor spent fuel over the past several decades, about one third has been used. Currently, about 200 tons of plutonium sits at reprocessing plants around the world – equivalent to the amount in some 30,000 nuclear weapons in global arsenals.

Recycled Uranium

In 2007 the International Atomic Energy Agency concluded that “reprocessed uranium currently plays a very minor role in satisfying world uranium requirements for power reactors.” In 2004, about 2 percent of uranium reactor fuel in France came from recycling, and it appears that it now has dwindled to zero. There are several reasons for this.

Uranium, which makes up about 95 percent of spent fuel, cannot be reused in the great majority of reactors without increasing the levels of a key source of energy, uranium 235, from 1 to 4 percent, through a complex and expensive enrichment process.

Reprocessed uranium also contains undesirable elements that make it highly radioactive and reduces the efficiency of the fuel. For instance, the build up of uranium 232 and uranium 234 in spent fuel creates a radiation hazard requiring extraordinary measures to protect workers. Levels of uranium-236 in used fuel impede atom splitting; and to compensate for this “poison, recycled uranium has to undergo costly “over-enrichment.” Contaminants in reprocessed uranium also foul up enrichment and processing facilities, as well as new fuel. Once it is recycled in a reactor, larger amounts of undesirable elements build up – increasing the expense of reuse, storage and disposal. Given these problems, it’s no surprise that DOE plans include disposal of future reprocessed uranium in landfills, instead of recycling.

Costs

As a senior energy adviser in the Clinton administration, I recall attending a briefing in 1996 by the National Academy of Sciences on the feasibility of recycling nuclear fuel. I'd been intrigued by the idea because of its promise to eliminate weapons-usable plutonium and to reduce the amount of waste that had to be buried, where it could conceivably seep into drinking water at some point in its multimillion-year-long half-lives.

But then came the Academy's unequivocal conclusion: the idea was supremely impractical. It would cost up to $500 billion in 1996 dollars and take 150 years to accomplish the transmutation of plutonium and other dangerous long-lived radioactive toxins. Ten years later the idea remains as costly and technologically unfeasible as it was in the 1990s. In 2007 the Academy once again tossed cold water on the Bush administration’s effort to jump start nuclear recycling by concluding that “there is no economic justification for going forward with this program at anything approaching a commercial scale.”

Meanwhile, the client base for Areva, the French nuclear recycling company, has shrunk to one new contract for a relatively small amount of spent fuel from the Netherlands. Most revealing is that its main customer, the French utility, Electricité de France, is balking at doing further business unless the price goes down something that Areva says it can’t do. It appears that even the French may be starting to say no instead of oui.

Robert Alvarez, a former Senior Advisor in the Department of Energy during the Clinton administration, is a Senior Scholar at the Institute for Policy Studies.

 

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Published by Foreign Policy In Focus (FPIF), a project of the Institute for Policy Studies (IPS, online at www.ips-dc.org). Copyright © 2008, Institute for Policy Studies.

Recommended citation:
Robert Alvarez, "Nuclear Recycling Fails the Test," (Washington, DC: Foreign Policy In Focus, July 7, 2008).

Web location:
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Production Information:
Author(s): Robert Alvarez
Editor(s): Miriam Pemberton
Production: Erik Leaver
















 

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Lyndon LaRouche!!!
http://www.schillerinstitute.org/economy/phys_econ/2006/beaut_nuke_cycle.html
The Beauty of Completing
the Nuclear Fuel Cycle

The U.S. pioneered the full nuclear fuel cycle, but gave it up in the 1970s, following a Ford Administration policy written under the direction of Dick Cheney.
Marjorie Mazel Hecht reports.1

Related Pages



The full nuclear fuel cycle shows that nuclear is a renewable energy source, because the spent fuel can be reprocessed to recover unburned uranium and plutonium that can be fabricated into new reactor fuel. At present, the U.S. nuclear is “once through,” going from spent fuel to interim storage and then longer-term storage.

It would take 2 million grams of oil or 3 million grams of coal to equal the power contained in 1 gram of uranium fuel.2 Unlike oil and coal, nuclear fuel is recyclable and, in a breeder reactor, can actually produce more fuel than is used up! For these reasons, nuclear energy is by far the best means now available to power a modern industrial economy.

Nuclear power is a gift to humanity, and only the propaganda of Malthusian extremists, dedicated to stopping human progress and reducing the world’s population, has created public fear and skepticism.

The best way to overcome irrational fear is through knowledge. To this end, reviewed here is the process by which natural uranium ore is turned into fuel for a nuclear reactor, how it is used, and how it can be recycled, such that the reader will come to understand that there is really no such thing as nuclear “waste.”

The Nuclear Fuel Cycle



DOE
An overhead view of rows of centrifuge units at a U.S. enrichment plant in Piketon, Ohio.

To understand the “renewability” of nuclear fission fuel, we have to look at the complete fuel cycle. At the beginning of the nuclear age, it was assumed that nations would complete the fuel cycle—including the reprocessing of spent nuclear fuel from reactors, to get as near to 100% use of the uranium fuel as possible. Here we very briefly review the seven steps of this cycle. Keep in mind that the brevity of description leaves out details of the complex chemical processes, which were initiated during the Manhattan Project and are still being improved on.

1. First, natural uranium is mined. There are enough sources of uranium worldwide for today’s immediate needs, but once we begin an ambitious nuclear development program (to build 6,000 nuclear reactors in order to provide enough electricity to bring the entire world population up to a decent living standard), we would have to accelerate the development of fast breeder nuclear reactors, which produce more fuel than they consume in operation.

2. Next, the uranium is processed and milled into uranium oxide (U3O8), called yellowcake, which is the raw material for fission fuel. Yellowcake became infamous in the political fabrication that Saddam Hussein’s Iraq was trying to import yellowcake from Niger, in order to use it for bomb-making.

It is basically natural uranium ore, which is crushed and processed by leaching (with acid or carbonate) to dissolve the uranium, which can then be extracted and concentrated to 75% uranium, in combination with ammonium or sodium-magnesium.

3. The concentrated uranium is then converted into uranium hexafluoride (UF6), which is heated into a gas form suitable for enrichment.

Uranium Enrichment

4. Natural uranium has one primary isotope, U-238, which is not fissionable, and a much smaller amount of U-235, which fissions. Because most uranium (99.276%) is U-238, the uranium fuel must go through a process of enrichment, to increase the ratio of fissionable U-235 to the non-fissionable U-238 from about 0.7% to 3 to 4%. (Weapons uranium is enriched to about 93% U-235.)

The technology of enrichment was developed during the World War II Manhattan Project, when the object was to create highly enriched uranium (HEU) to be used in the atomic bomb. Civilian power reactors use mostly low-enriched uranium (LEU). (Canada has developed a type of reactor, the CANDU, which uses unenriched, natural uranium in combination with a heavy water moderator to produce fission.)



Frank Hoffman/DOE
The huge Gaseous Diffusion Plant in Oak Ridge, Tenn., the first such facility in the world. The U-shaped building, constructed during the Manhattaan Project, began operation in 1945. Later, the facility was expanded to produce enriched uranium for plants around the world.

The gaseous diffusion method of enrichment, which is still used by the United States, was developed under the Manhattan Project. Uranium hexafluoride gas is pumped through a vast series of porous membranes—thousands of miles of them. The molecules of the lighter isotope (U-235) pass through the membrane walls slightly faster than do the heavier isotope (U-238). When extracted, the gas has an increased content of U-235, which is fed into the next membrane-sieve, and the process is repeated until the desired enrichment is reached. Because the molecular speeds of the two uranium isotopes differ by only about 0.4%, each diffusion operation must be repeated 1,200 times.

The Manhattan Project devised this method of gaseous diffusion with incredible speed and secrecy. It was not finished in time to produce all the uranium for the uranium bomb dropped on Japan, but it produced most of the enriched uranium for the civilian and military programs in subsequent years. Although a successful method, it required a tremendous amount of energy and a huge physical structure to house the “cascades” of separate membranes. Four power plants were built in Oak Ridge, Tenn., to power the process, producing as much electric power as the consumption of the entire Soviet Union in 1939! Almost all the power consumed in the diffusion process is used to circulate and compress the uranium gas.

Technological pessimists take note: At the time the gaseous diffusion plant was being built, scientists had not yet figured out how to make a membrane to be used in the process—but they did it in time to make it work!

The centrifuge system, used in Europe and Japan, is 10 times as energy efficient. The strong centrifugal field of a rotating cylinder sends the heavier isotope in uranium hexafluoride to the outside of the cylinder, where it can be drawn off, while the U-235 diffuses to the inside of the cylinder. Because of the limitations of size of the centrifuge, many thousands of identical centrifuges, connected in a series called a cascade, are necessary to produce the required amounts of enriched uranium.

A centrifuge plant requires only about 4% of the power needed for a gaseous diffusion plant, and less water is needed for cooling.

Other methods of enrichment are possible—electromagnetic separation, laser isotope separation, and biological methods.

Fabrication Into Fuel Rods

U.S. AEC
A cylinder of uranium hexaflouride enriched in U-235 is readied for shipment to a conversion facility, where it will be converted to uranium dioxide for use in fuel rods. The cylinder weighs 2.5 tons.
Westinghouse Photo
A partially completed nuclear fuel assembly. The long tubes guide the control rods in the reactor, which regulated its operation. The grids that hold the guide sheaths also align the fuel rods containing uranium pettets. When the fuel rods are inserted through the grids, parallel to the guide sheath, the fuel assembly will be completed.

5. Once the enriched uranium is separated from the depleted uranium, it is converted from UF6 into uranium dioxide and fabricated into uniform pellets. The pellets are loaded into long tubes made out of a zirconium alloy, which captures very few neutrons. This cladding prevents the release of fission products and also transfers the heat produced by the nuclear fission process in the fuel. The fuel is then transported to the reactor site.

Different types of reactors require different designs of fuel rods and fuel bundles. In a light water reactor, the fuel rods are inserted into the reactor to produce fission, which creates steam, which turns a turbine that creates electricity.

The fuel for the next-generation high-temperature gas-cooled reactors is different: The enriched uranium is formed into tiny “pebbles” which are coated with graphite and special ceramics that serve as individual “containment buildings” for the fuel pebbles.

6. Fuel rods are used for about four and a half years before replacement, and usually a reactor replaces about a third of its fuel at one time. The fuel is considered spent when the concentration of fissile uranium-235 becomes less than 1%. When removed from the reactor, the spent fuel is put into cooling pools, which shield it as its short-lived nuclides decay. Within a year, the total radioactivity level is only about 12% of what it was when the fuel rod came out of the reactor.

At present, the United States does not reprocess spent fuel, and so the spent fuel rods sit in cooling pools at the reactor. After the spent fuel has cooled, it is stored in dry casks, waiting—for “burial” or reprocessing.

But the spent fuel is not “waste”! It contains between 90 and 95% of usable uranium, that can be separated out and recycled into new fuel, and it also contains a smaller amount—about 1%—of plutonium, a fuel for breeder reactors.

Reprocessing



Nuclear Materials and Equipment Corporation
In this 1964 photo, laboratory technicians work in glove-boxes to remotely fabricate plutonium fuel elements.

7. Now for the remarkable renewability of nuclear fuel. The spent fuel from a single 1,000-megawatt nuclear plant, operated over 40 years, is equal to the energy in 130 million barrels of oil, or 37 million tons of coal. Why bury it? Extract it and process it into new fuel. Short-sighted policymakers (discussed below) decided in the 1970s, for no good reasons, that it was preferable to prevent the full use of this potential by burying the spent fuel in a once-through cycle.

The reprocessing method that was successfully used in the United States at the Savannah River facility in South Carolina for military purposes, is just as efficient for civilian spent fuel. Spent fuel rods are processed to remove the highly radioactive fission products, and separate out (partition) the fissionable U-235 and plutonium.

This plutonium could be directly used as fuel for breeder reactors, which was the intention of the completed fuel cycle. It can also be used to make mixed-oxide fuel, or MOX, which some of today’s reactors are being converted to burn as fuel. (Thirty-five reactors in Europe now use MOX fuel.)

The reprocessing facilities at Savannah River were called “canyons” because they were tall, narrow buildings. The spent nuclear fuel was handled remotely by technicians who were behind protective walls. This was large-scale industrial processing, which was entirely successful, safe, and safeguarded.

Once the uranium was separated out, it was sent to another building at Savannah River to be fabricated for weapons use. The remaining amount of highly radioactive fission products—a tiny fraction of the spent fuel—was set aside for vitrification and storage. Today, the technologies exist, or could be developed, to extract valuable medical and other isotopes from this 3% of high-level waste. Virtually all of the spent fuel could be made usable.

U.S. civilian spent fuel could be reprocessed in a similar fashion using the Savannah River model—or by new technologies still to be developed.3 Right now, Britain, France, Russia, and India reprocess civilian spent fuel, using the Purex method (which stands for Plutonium Uranium Extraction), and Japan has a commercial reprocessing plant now in a testing start-up phase. Other nuclear nations send their spent fuel to Britain or France for reprocessing, or they store it. China reprocesses military spent fuel.

Who Opposes Reprocessing?



E.I. DuPont DeNemours &Co.
A 1972 photo of high-level waste storage tanks in construction at DOE’s Savannah River Plant in South Carolina. The tanks are built of carbon steel, surrounded by concrete encasements 2 to 3 feet thick, set about 40 feet in the ground and then covered with dirt. Shown are the steel tanks before concrete encasement. Each tank has a capacity of from 750,000 to 1,300,000 gallons.

Reprocessing makes the antipopulation faction very nervous, because it implies that nuclear power will continue to develop as a source of electricity, and with a cheap and clean source of power, there are no limits to growth. Malthusians and other alarmists rant about the “dangers of proliferation,” but if you poke them, what they are really concerned about is the potential for nuclear energy to expand, and population and industrial development to grow.

The overt arguments against reprocessing are mostly scare tactics: Permitting U.S. reprocessing will make it easier, they say, for “bad guys” to build bombs—or dirty bombs. This is the gist of the objection, although it may be posed at length in more academic (and tedious) language.

But this argument is one based on fear—fear that an advanced technology can never be managed properly, and fear that we will never have a world where there aren’t “bad guys” who want to bomb us. It is the opposite of the Atoms for Peace philosophy.

In fact, if one is truly worried about diversion of plutonium, why not burn it to produce electricity, instead of letting it accumulate in storage? And as Savannah River manager William P. Bebbington, a veteran of the Manhattan Project, wrote in a landmark 1976 article on reprocessing, “Perhaps our best hope is that someday plutonium will be more valuable for power-reactor fuel than for weapons, and that the nations will then beat their bombs into fuel rods.”4

A second objection is that reprocessing is not “economical”; it is cheaper to have a “once through cycle” and discard the spent fuel. But the cost/benefit basis on which such economics are calculated is a sham. What is the cost of not reprocessing—in terms of lives lost and society not advancing? And what about the cost of the storage of spent fuel—not to mention the still unused U.S. storage facility at Yucca Mountain, Nevada, which has become a costly political and emotional football.

The “proliferation” argument was key in 1976 in stopping U.S. reprocessing. Fear was fed by the idea that reprocessing would make more plutonium available, which could be diverted by “rogue” nations or groups to make clandestine nuclear weapons. President Ford, the incumbent, carried out a secret study, and issued a nuclear policy statement on Oct. 28, 1976, just five days before the election, which advocated an end to reprocessing.

Jimmy Carter, who won that election, then carried out the policy to stop U.S. reprocessing; and the next President, Ronald Reagan, sealed the lid on the fuel-cycle coffin with the idea of “privatizing” both reprocessing and breeder reactors.

The full story of how reprocessing was stopped still has to be told. But the ending of the story is clear: The United States shot itself in the foot—twice: 1) The United States stopped an important technology, which this country had pioneered, and 2) the U.S. anti-reprocessing policy did absolutely nothing in the rest of the world to stop other countries from developing the full nuclear fuel cycle, or desiring to.5

Interestingly, the Ford Administration’s policy in 1976, which advocated killing U.S. reprocessing for the same fallacious reasons that President Carter later elaborated, was written under the direction of Ford’s chief of staff—Dick Cheney. And one of the key reports supporting Carter’s ban on reprocessing was written by the mentor of the leading neo-cons in the Bush Administration, Albert Wohlstetter, then a consultant to the Department of Defense.

Once the political decision is taken to begin an ambitious nuclear construction program, reprocessing—both Purex and new technologies—will follow.


For Further Reading

Scott W. Heaberlin, A Case for Nuclear-Generated Electricity ... or why I think nuclear power is cool and why it is important that you think so too (Columbus, Oh.: Battelle Press, 2004).

Alan Waltar, Radiation and Modern Life (Amherst, N.Y.: Prometheus Books, 2004).

See also: http://www.world-nuclear.org/education/education.htm on the fuel cycle.

1. Reprinted from 21st Century Science & Technology, Winter 2005-06. See www.21stcenturysciencetech.com.

2. The energy density of nuclear can be seen by comparing fission fuel to other sources. In terms of volume of fuel necessary to do the same amount of work, a tiny pellet (1.86 grams) of uranium fuel equals 1,260 gallons of oil, or 6.15 tons of coal, or 23.5 tons of dry wood. This means that nuclear is 2.2 million times more energy dense than oil, and 3 million times more energy dense than coal. Thermonuclear fusion will be even orders of magnitude more energy dense. These calculations were based on the work of Dr. Robert J. Moon in 1985.

3. The U.S. Congress in the 2005 Energy Act included $50 million for research on new reprocessing methods.

4. “The Reprocessing of Nuclear Fuels” by William P. Bebbington, Scientific American, December 1976, pp. 30-41.

5. Commenting on President Carter’s 1977 policy to shut down reprocessing and the Clinch River Breeder Reactor, Bernard Goldschmidt, a preeminent French nuclear scientist, who had studied with Marie Curie, wrote: “By this extraordinary and unique act of self-mutiliation, an already declining American industry was to become paralyzed in two key sectors of future development, fuel reprocessing and breeder reactors, precisely the sectors in which the United States was already between 5 and 10 years behind the Soviet Union and Western Europe, in particular, France....”








http://www.newscientist.com/blog/environment/2007/05/uk-signals-abandonment-of-nuclear-fuel.html

Wednesday, May 23, 2007

UK signals abandonment of nuclear fuel reprocessing

Amidst all the palaver over the UK government's energy policy paper backing a new programme of nuclear power stations on Wednesday, one significant shift has so far been missed. Buried away on page 204 is a change that will give anti-nuclear campaigners some crumbs of comfort.

"The Government has concluded," it says, "that any nuclear power stations that might be built in the UK should proceed on the basis that spent fuel will not be reprocessed." This is the clearest statement so far of ministers' intention to abandon the decades-old policy of reprocessing uranium burnt in reactors.

All the fuel from Britain's first and second generation nuclear stations has been chemically separated into uranium, plutonium and radioactive waste at Sellafield in Cumbria. Only spent fuel from one station - the pressurised water reactor at Sizewell in Suffolk (pictured) - has not been reprocessed.

But the new government energy paper says that reprocessing "raises particular concerns about the creation of separated plutonium". It also points out that the private sector "has made no proposals to reprocess spent fuel from many new nuclear power stations."

Reprocessing at Sellafield has been dogged with problems, with the main plant shut down since April 2005 following a leak of 83,000 litres of highly radioactive nitric acid. A plan to restart the plant earlier in 2007 had to be postponed when problems were discovered with downstream evaporators.

The government's decision to end reprocessing will not be welcomed at Sellafield, though neither the plant's operator, the British Nuclear Group, nor its owner, the Nuclear Decommissioning Authority, wanted to comment.

The abandonment of reprocessing would represent a small victory for the anti-nuclear lobby which has long targeted Sellafield's operations as polluting and unnecessary. But Greenpeace points out that it will leave the government with new problems to solve - like where to store and how to dispose of the spent fuel. That looks like more bad news to be buried in the future.

Rob Edwards, New Scientist consultant






http://www.globalsecurity.org/wmd/world/dprk/nuke-plutonium.htm

Plutonium Program

Estimates vary of both the amount of plutonium in North Korea's possession and number of nuclear weapons that could be manufactured from the material. Official estimates of the amount of reproccessed plutonium reportedly range from 7 to 24 kilograms, and the amount of plutonium that North Korea would need for a single bomb range from 4 to 8 kilograms. Thus, by one calculation North Korea might have as many as six nuclear weapons, if it could use 24 kilograms to make 4 kilogram bombs. Or it might barely fall short of being able to make a single bomb, if it had only 7 kilograms when it needed 8 kilograms of plutonium.

South Korean, Japanese, and Russian intelligence estimates of the amount of plutonium separated, for example, are reported to be higher -- 7 to 22 kilograms, 16 to 24 kilograms, and 20 kilograms, respectively -- than the reported US estimate of about 12 kilograms. At least two of the estimates are said to be based on the assumption that North Korea removed fuel rods from the 5-MW(e) reactor and subsequently reprocessed the fuel during slowdowns in the reactor's operations in 1990 and 1991.

In principle the North Korea 5-MW(e) reactor would produce 0.9 gram of Plutonium per thermal megawatt every day of operations. When the yearly operations rate [capacity factor] is presumed to be 85 percent, the actual amount produced each year would be between 5.5 and 8.5 kilograms [given the range of estimates of between 20 and 30 megawatts thermal output. A lower, and possibly more realistic, estimate based on a capacity factor of 60 percent would suggest an annual production rate of between 4 and 6 kilograms.

In 1989, the reactor was shut down for a period variously estimated at between 70 and 100 days, and this would have provided enough time for North Korea to unload some or all of the fuel for reprocessing. By this time, the total production could have been somewhere between 8 and 15 kilograms of plutonium. North Korea claims that it only removed a few damaged fuel rods, which were reprocessed in the Radiochemical Laboratory in 1990. According to the North, these contained about 0.13 kilograms of plutonium, of which only a 0.09 kilograms were extracted.

When the reactor was shut down for refueling in April 1994, it was variously estimated that the unloaded spent fuel contained 17 to 33 kilograms of weapon-grade plutonium. The 8,000 spent fuel rods at the Yongbyon facility are in special canisters, under the watchful eye of the International Atomic Energy Agency 24 hours a day. Those eight thousand spent fuel rods contain enough plutonium for the North Koreans to build up to perhaps as many as six additional nuclear weapons. Absent international safeguards, North Korea could begin reprocessing the spent fuelinto plutonium for atomic bombs in six to eight months, according to some estimates.

The variations in the estimates about the number of weapons that could be produced from the material depend on a variety of factors, including assumptions about North Korea's reprocessing capabilities -- advanced technology yields more material -- and the amount of plutonium it takes to make a nuclear weapon. Until January 1994, the Department of Energy (DOE) estimated that 8 kilograms would be needed to make a small nuclear weapon. In January 1994, however, DOE reduced the estimate of the amount of plutonium needed to 4 kilograms.

On 22 April 1997, US Defense Department spokesman Kenneth Bacon officially stated, "When the US-North Korea nuclear agreement was signed in Geneva in 1994, the US intelligence authorities already believed North Korea had produced plutonium enough for at least one nuclear weapon." This was the first time the United States confirmed North Korea's possession of nuclear weapons.

According to a late 2002 CIA analysis, "Restarting the 5 megawatt reactor would generate about 6 kilograms [of plutonium] per year. ... The 50 megawatt-electric reactor at Yongbyon and the 200 megawatt-electric reactor at Taechon would generate about 275 kilograms per year, although it would take several years to complete construction of these reactors." If about 5 kilograms of plutonium was required for one bomb, the North Korean bomb-production rate would thus be about 55 weapons per year after the reactors are completed. ["North Korea Can Build Nukes Right Now," By Bill Gertz, The Washington Times, November 22, 2002 Pg. 1].

A story in the New York Times on July 20, 2003 reported that US intelligence officials believe that North Korea may have a second facility that could produce weapons-grade plutonium. The second facility is believed to be buried underground at an unknown location. The story, "North Korea Hides New Nuclear Site, Evidence Suggests" by David E. Sanger and Thom Shanker New York Times reported that sensors on North Korea's borders have begun to detect elevated levels of krypton-85, a gas emitted as spent fuel is converted into plutonium. The report says the issue that most concerns American and Asian officials, though, is analysis showing that the gas is not coming from North Korea's main nuclear plant, Yongbyon. Instead, the experts believe the gas may be coming from another hidden facility, buried deep in the mountains. North Korea is believed to have 11-15,000 underground military-industrial facilities.

The September 1, 2003 edition of Jane's Intelligence Review reports that the director of the the ROK's National Intelligence Service stated to the National Assembly in early July 2003 that North Korea had conducted 70 high-explosive tests at Yondok, 40km northwest of Yongbyon. Such high explosives could be used in plutonium device by compressing the plutonium core to create a nuclear explosion.

On 02 October 2003 North Korea said it had reprocessed eight thousand nuclear fuel rods and plutonium extracted from them could be used to strengthen its "nuclear deterrent force." A statement from the North Korean foreign ministry carried by the official Korean Central News Agency said that North Korea is manufacturing nuclear bombs with the material siphoned off from reprocessing eight thousand spent nuclear fuel rods. North Korea's latest claim came days after it warned it was taking "practical measures" to increase its nuclear deterrent against attacks by the United States. At the same time, a senior North Korean official reportedly said that his government will not export its nuclear capability. Vice Foreign Minister Choe Su Hon, said that Pyongyang does not intend to transfer its nuclear know-how to other countries.

During a visit to Yongbyon on 08 January 2004, North Korea showed an unofficial American delegation what it asserted was weapons-grade plutonium. The group spent about a day at Yongbyon, and was shown the empty cooling pond where the 8,000 fuel rods from the 5-megawatt nuclear reactor had been stored. During the visit, the reprocessing plant was operating.

In January 2004 DPRK Vice Minister of Foreign Affairs Kim Gye Gwan indicated that the DPRK had decided in November 2002 to operate the 5MWe reactor and resume reprocessing of plutonium for peaceful nuclear activities. He stated, “It is the only way to keep the spent fuel rods safe.” He added, “At the same time, the hostile U.S. policy had been intensified. So, we changed our purpose and informed the U.S. that the plutonium that was to have been used for peaceful purposes would now be used for weapons. Originally, we had wanted to keep the reprocessed plutonium in a way we could store it safely. Then, we changed the purpose in order to strengthen our deterrent.” During the 08 January 2004 visit of the American delegation, the North Koreans stated that they had initially intended to run the fuel cycle for civilian purposes, which means they would have stored the plutonium product as plutonium dioxide. Because of the "hostile U.S. actions" they reprocessed the entire campaign to plutonium metal. [Hecker testimony]

During the 08 January 2004 visit of the American delegation, the North Koreans stated that they reprocessed all 8000 spent fuel rods in the Radiochemical Laboratory in one continuous campaign, starting in mid-January 2003 and finishing by the end of June 2003. They stated that their capacity in the Radiochemical Laboratory is 375 kg uranium per day (they said they worked four 6-hr shifts around the clock). They later added that the reprocessing capacity of the facility under normal operating conditions is 110 tonnes of spent uranium fuel per year. Therefore, they were able to finish the current campaign of 50 tonnes of spent fuel rods in less than six months. They reprocessed the entire campaign to plutonium metal. They stated that this processing was done in the Radiochemical Laboratory by installing some glove boxes that were not present during IAEA inspections. It took them three months to install the equipment and prepare it for the plutonium metal processing step. These comments indicated that they had glove boxes for plutonium metal production ready to go in late 2002. This also indicated that they had experience making plutonium metal before the IAEA inspections began in 1992. The American delegation was shown the “product” from what the North Koreans claimed to be their most recent reprocessing campaign -- a wooden box with a glass jar they said contained 150 grams of plutonium oxalate powder and a glass jar they said contained 200 grams of plutonium metal for the Americans to inspect. [Hecker testimony]

US author and Korea expert Selig Harrison, completed a visit to Pyongyang in April 2005 that included talks with senior figures, including Kim Yong Nam, the country's second-ranking official. Harrison, of Washington's Center for International Policy, was reportedly told that North Korea would soon again harvest plutonium from fuel rods at its Yongbyon nuclear reactor, giving it enough nuclear explosive to build several more bombs.



http://www.stormsmith.nl/

Nuclear power – the energy balance

 

Jan Willem Storm van Leeuwen

Senior Scientist

Ceedata Consultancy

Chaam, Netherlands

storm@ceedata.nl

 

 

February 2008

 

This report is an update of the original report published on this website:

Nuclear power the energy balance

by Jan Willem Storm van Leeuwen and Philip Smith

 The original report is still available on this website: see below.

 

 

In this update the author gratefully incorporated numerous valuable comments and critical questions from independent consultants, NGOs and scientists at large companies and at universities and scientific institutions. A short selection:

Australia: University of Sydney, University of New South Wales, Monash University.

Belgium: NPX Research Leuven, IMEC Leuven.

Germany: Universität Regensburg, Öko Institut Darmstadt.

Netherlands: University of Utrecht, Technical University Eindhoven, ECN Petten.

Switzerland: CERN Geneva, ETH Zürich.

United Kingdom: Imperial College London, University of Edinburgh, Oxford Research Group London.

United States of America: Brookhaven National Laboratory, Columbia University New York, Princeton University.

 

 

Objectives of this study

 

This study is aiming to present in the most accessible way the scientific and physical aspects of nuclear power, that are relevant for its role as energy source in our society.

Here we address two main issues:

• The potential contribution of nuclear power to the world energy supply in the future, from a physical point of view.

• To what extent nuclear power could contribute to the mitigation of the anthropogenic climate change in the future.

Safety issues and proliferation risks are not directly addressed.

 

The sheer complexity of the nuclear system turns out to be a major hurdle in understanding the many different aspects of the civil application of nuclear power. Free access to all information, prerequisite for conscious choices by the civil policy makers, happens, is very difficult.

A number of nuclear institutes which policy makers and governments rely on for information regarding nuclear affairs, such as WNA (World Nucear Association), NEI (Nuclear Energy Institute), UIC (Uranium Information Centre) and IAEA (International Atomic Energy Agency), are organisations with a vested interest in nuclear power. These institutes are directed towards promoting nuclear energy, and are not necessarily neutral scientific institutes.

 

 

Summary

 

Nuclear power is not just an energy technology. Nuclear power is a unique complex of technical, economical, political and military interests.

Technically the nuclear energy system is by far the most complex energy system ever designed. Apart from its technical complexity, the nuclear system is also unique by its exceedingly long stay time. The completion of the sequence of activities related to one commercial nuclear power station, here called a nuclear project, from the start of construction through the safe disposal of its last radioactive waste, may take 100-150 years.

 

This study is a physical analysis of the nuclear system: the full technical and industrial complex, needed to generate electricity from uranium. The main issues are the potential contribution of nuclear power to the world energy supply in the future and to the mitigation of the anthropogenic climate change in the future. Safety issues and proliferation risks are not directly addressed.

We analyzed all energy inputs needed to operate the nuclear system and balanced these inputs with the energy output of the nuclear reactor: the amount of electricity put into the grid. Furthermore we analyzed the main parameters determining the energy balance, of which the grade of the uranium ore turned out to be the most important.

 

Some novel concepts are introduced, to make the results of this study better accessible: the, the ‘energy cliff’, the ‘CO2 trap’, the ‘coal ceiling’ and the ‘energy debt’. Beyond the energy cliff the nuclear system cannot generate net useful energy and will produce more carbon dioxide than a fossil-fueled power station (CO2 trap). Nuclear power may run off the energy cliff with the lifetime of new nuclear build.

Beyond the coal ceiling more uranium ore has to be processed each year to feed one nuclear power plant than the annual coal tonnage of coal consumed by a coal-fired power plant to generate the same amount of electricity.

 

The exceedingly large and long-term energy debt, combined with the insecurities of the nuclear energy system will seriously delay the transition of the world energy supply to a really sustainable one. A delay we cannot afford. The nuclear option would absorb a disproportionate part of the ability to cope of the society in a ever diverging need for energy, high quality materials and human skills.

 

The ease with which the nuclear industry waives the unsolved problems of nuclear power suggests an attitude of ‘après nous le déluge’.

 

Misconceptions

 

Discussions on nuclear power often are troubled by implicite but persistent misconceptions:

•  Ultimately every uranium atom in the ground or sea could be recovered, with no or a negligible energy input.

• Almost every uranium atom extracted from the ground or sea could be fissioned.

Both assumptions are false and easy to refute by applying basic physical laws, as is shown in this study.

A third, also implicite, misconception seems the view of many people talking about electricity generation thinking they’re talking about the whole energy supply.

 

 

Unique features of the nuclear system

 

The nuclear system has some unique features, no other energy system has, being:

•  the energy source is a metal to be extracted from ores,

•  the irreversible generation of immense quantities of radioactivity,

•  the extremely long-term commitments of 100-150 years,

•  very large uncertainties regarding the completion of a nuclear project.

Once started, a nuclear reactor generates unavoidable and very large amounts of radioactive waste, posing immeasurable risks to man and society. The safe cleanup of the nuclear legacy requires a number of processes, each consuming large amounts of materials, human effort and energy.

Energy is a conserved quantity, whereas the value of money is unpredictable beyond a very short time horizon. Energy debts cannot just be written off as uncollectable. Just for that reason we choose for energy analysis as our tool.

 

 

Methodology of this study

 

This study comprises a full life cycle assessment (LCA) and energy analysis of the technical/industrial system which makes possible the generation of electricity from uranium. The LCA is based on the light-water reactor (LWR) in the once-through mode.

All data used in the analysis originate from the open literature of the nuclear industry itself.

Due to the many variables involved, the full energy analysis of the nuclear system is complicated.

The methodology used in this study has been validated by numerous peer reviewed publications in the 1970s and 1980s. One of us (Storm van Leeuwen) published the results of an earlier study based on the same methodology in Energy Policy, June 1985 (click here to download a pdf copy (877 kB).

 

 

History of this study

 

The study started in 2000, on request of the Green parties of the European Parliament, to prepare a background document for the UN Climate Conference COP6 (The Hague, 13-24 November 2000).

After that conference the results were placed on the web in 2001. Since its first publication the study has seen several revisions. We thank our readers all over the world who sent us, and are still sending, their comments.

You can contact us at the email address storm@ceedata.nl

 

 

Publications

 

Short selection of recent publications on nuclear power.

 

A new paradigm. Climate change and nuclear power,

presentation at the Institute of Physiscs, London, 9 March 2006,

www.iop.org

 

Climate change and nuclear power,

CERN, Geneva, April 2006

http://ihp-lx2.ethz.ch/energy21/Links.html

 

Published by the Oxford Research Group, London, 2006, 2007

Energy from uranium (1023 kB)

Factsheet 4: Energy security and uranium reserves (877 kB)

Secure energy? Civil nuclear power, security and global warming( (1.3 MB)

See also:

www.oxfordresearchgroup.org.uk

 

presentation: Nuclear power and global warming (1.5 MB)

Seminar Kernenergie in de 21ste eeuw. Realiteit en beloften,

Brussels, Federaal Parlement, 19 Oktober 2006

Greenpeace, WWF, IEW, Bond Beter Leefmileu, Voor Moeder Aarde.

See also:

www.uitstapkernenergie.be/

www.greenpeace.org/belgium/

 

Atomstrom ist keine Lösung für Klimaprobleme und Energieknappheit, (239 kB)

Energie und Umwelt, Dezember 2006 (in German).

See also:

www.energiestiftung.ch/

 

 

Reviews

 

The original study has been extensively reviewed by ISA of the University of Sydney:

Life-Cycle Energy Balance and Greenhouse Gas Emissions of Nuclear Energy in Australia,

A study undertaken for the Department of Prime Minister and Cabinet of the Australian Government,

ISA, The University of Sydney, 3 November 2006,

http://www.dpmc.gov.au/publications/umpner/docs/commissioned/ISA_report.pdf

 

Zittel W & Schindler J,

Uranium Resources and Nuclear Energy,

Energy Watch Group, EWG Paper 1/06, December 2006,

www.energywatchgroup.org

 

 

Critique

 

Critique and rebuttal:

www.nuclearinfo.net

 

Critique:

www.world-nuclear.org/info/inf11.htm

Rebuttal

In 2003 we added a Rebuttal to our site. This document refutes criticism that was placed on the web by the nuclear industry, the World Nuclear Association, WNA (www.world-nuclear.org ), in an attempt to discredit the conclusions reached in an earlier version of this website. Every point of criticism is completely refuted with facts and calculations, all based on publications of the industry itself.

It is unpleasant to note that some of the criticism was based on apparently deliberate misquotation of our text. The criticism of WNA has been updated several times since its first appearance on the web.

 

Nuclear power – the energy balance

 

Table of contents

Due to its length the new report has been divided into  a number of parts (labeled A, B, C, . . .), which can be downloaded separately. Each part addresses certain aspects or phases of the study and may be updated later on, independently of the other parts. Each part has its own list of references, each reference being coded with a unique code (e.g. Q6) which is used throughout the publications of the author.

 

Part A  (pdf 280 kB) October 2007

Nuclear power in its global context

To place nuclear power in its global context, the current nuclear share of world energy supply and greenhouse gas mitigation is addressed. A confusing manipulation of statistical data is widely used in the official energy statistics, which actually is in conflict with the First Law of thermodynamics. The nuclear share in 2006 was 2.1% of the world energy supply. Consequently, assumed nuclear power is free of greenhouse gases (which it is not), the nuclear contribution to the mitigation of the anthropogenic emissions of greenhouse gases would be at most 2.1%.

References

 

Part B (pdf 512 kB) October 2007

The reference reactor

B1        Which technology?

B2        Primary reactor parameters

B3        Load factor and operational lifetime

B4        Secondary reactor parameters

B5        The nuclear system

References

 

Part C (pdf 668 kB) October 2007

Energy analysis – the method

C1        Methodology

C2        Energy balance of the nuclear system

C3        Performance parameters

C4        Energy debt and CO2 debt

C5        Other greenhouse gases

References

 

Part D (pdf 1 MB) October 2007

Uranium

D1        World known recoverable uranium resources

D2        World known recoverable uranium resources by grade

D3        Recovery of uranium from the earth’s crust

D4        Energy requirements of uranium recovery

D5        In situ leach (ISL) uranium mining

D6        Mine reclamation

D7        Process analysis of the Ranger mine

D8        Olympic Dam

D9        Uranium from unconventional resources: phosphates, shales and granites

D10      Uranium from seawater

D12      MOX fuel

D11      World uranium outlook

References

Part E (pdf 640 kB) October 2007

Energy analysis – process data

E1        Nuclear process chain: outline and uranium mass balance

E2        Processes of the nuclear chain

E3        Summary tables of the basic chain parameters

References

Part F (pdf 1.2 MB) December 2007

Reactor: construction

operation, maintenance and refurbishments

decommissioning and dismantling

F1        Construction cost

F2        Construction materials requirements

F3        Construction energy - other studies

F4        Construction energy - methodology and results

F5 Operation, maintenance and refurbishments

F6        Decommissioning and dismantling

References

Part G (pdf 1.3 MB) January 2008

Energy analysis – results

G1        Outline of the energy analysis

G2 System parameters with a fixed value

G3        Energy inputs of the first core

G4        Energy inputs of one reload charge

G5        Lifetime parameters

G6        Energy cliff, CO2 trap and energy debt

References

Part H (pdf 672 kB) February 2008

The future of nuclear power

H1        Scenarios

H2        Depletion of the known uranium resources

H3        Uranium supply in the future

H4 Uranium supply: conclusions

References

 

 

Original report (August 2005)

Jan Willem Storm van Leeuwen and Philip Smith

Table of contents

 

About the authors

Contains short curricula vitae of the authors.

 

Introduction (410 kB).

In the Introduction we describe the methodology followed in our analysis. The advantages of a life-cycle analysis (LCA) of nuclear power plants are compared with an analysis based on consideration of monetary cost/benefit studies. The fundamental physical criteria for sustainability are presented as grounded in the first and second law of thermodynamics. An overview of the energy costs is given. The technical parameters used in the analysis of a nuclear power plant are also given, for the operating mode of a nuclear reactor (system) under the currently applied high efficiency mode.

 

Chapter 1 (151 kB)

The CO2-emission of the nuclear life-cycle

We devote Chapter 1 to one of the most controversial issues in the current environmental debate: the emission of CO2. We calculate the ratio of the CO2 emission brought about by the use of nuclear energy and that of a gas-burning plant of the same net (electrical) capacity.

If the uranium consumed by the nuclear energy system has been extracted from rich ores the ratio CO2(nuclear/CO2(gas) is much less than unity, giving the impression that the application of nuclear energy would solve the global warming problem.

However as rich ores become exhausted this ratio increases until it finally becomes larger than one, making the use of nuclear energy unfavourable compared to simply burning the (remaining) fossil fuels directly. In the long term the use of nuclear energy provides us with no solution to the problem.

 

Chapter 2 (348 kB)

From ore to electricity. Energy production and uranium resources

In the second chapter the energy requirements of the nuclear fuel (enriched uranium) is given on the basis of figures from the nuclear mining industry. All industry estimates of the energy costs of energy are based on rich uranium ores. The energy costs of the mining and milling of rich ores is negligible compared to the other energy costs of operating a nuclear power plant, as well as with respect to the energy produced by the power plant. The total energy available from these ores, as listed by the World Nuclear Association, is so small that in order to give a fair picture for the future, one must consider the energy costs of leaner ores.

It turns out that the energy requirements of mining and milling these lean ores may surpass the energy produced by "burning" them in a nuclear reactor.

 

Chapter 3 (128 kB)

The Power Plant

In the third chapter the energy inputs of construction, operating, and decommissioning a nuclear power plant are calculated, assuming 2000 as the year of commissioning.

The costs of decommissioning are lumped together with the construction costs, since even though these costs may actually be incurred fifty or a hundred years after the reactor has stopped producing energy, they should properly be subtracted from the energy produced during the useful lifetime of the plant. For this reason we label them "energy debts". The time at which these energy debts must be paid is irrelevant, quite differently than monetary debts. The latter are, in economic calculations, discounted at an assumed interest rate, and are further subject to the variations in the value of money. It is here that one sees the great value of energy analysis as compared to monetary analysis. Energy is a conserved quantity, whereas the value of money is unpredictable beyond a very short time horizon. Energy debts cannot just be written off as uncollectable.

 

Chapter 4 (69 kB)

Radioactive Waste; conditioning and disposal

In the fourth chapter the energy costs of the safe sequestration of the immense amounts of radioactive substances produced by nuclear power are calculated. These calculations must, of necessity, be approximate since the gargantuan task of safe disposal has hardly been begun.

 

Chapter 5 (96 kB).

Technical/Mathematical Summary of Formulas

In the fifth chapter an overview of the formulas used in our study is given for reference.

 

References

This file contains all of the literature references used in our study.

 

 






http://www.michaelhopping.com/features/OntheRoad.html


Going on the road?

nuclear fuel reprocessing proposed for US

 

The Indie 5:51, June 1, 2007

The US nuclear power industry, forced into dormancy almost thirty years ago by the partial meltdown at Three Mile Island, is positioning itself for a revival. Despite objections that the nuclear fuel cycle has been demonstrated to produce significant greenhouse gas emissions, is far more expensive per megawatt than renewable technologies and energy efficiency programs, and that new nukes would take at least a decade to begin coming on-line, some environmentalists have joined the Bush administration in proclaiming nuclear power to be part of the solution to global warming.

In January, 2006, President Bush announced his vision for our nuclear future, the Global Nuclear Energy Partnership (GNEP). GNEP proposes to build new nuclear plants using “advanced burner” technology and to reprocess the spent fuel now piling up at commercial reactor sites. The United States would also get into the business of reprocessing spent fuel from other countries willing to lease fuel rods from us rather than develop their own nuclear power programs.

John Sticpewich, an Asheville-area resident and retired oil and gas industry geologist, became curious about the consequences for Asheville if a South Carolina location were chosen for the spent fuel reprocessing plant GNEP calls for. (Of the eleven sites under study, the Savannah River Site and nearby Barnwell are both in SC.) At a Common Sense at the Nuclear Crossroads press conference announcing his findings, Sticpewich said, “I came to the study with a healthy case of skepticism and ended with an unhealthy case of horror.”

Reprocessing
When uranium fuel rods outlive their usefulness in the core of a nuclear reactor, they’re removed intact in their assemblies and immediately stored underwater in cooling pools. This is necessary because the fission chain-reaction continues. The rods remain hot enough to melt and or burn. Over the next five or so years, a buildup of fractured atoms within the rods slows the reaction sufficiently to permit dry storage in heavily shielded casks. Meanwhile, the atomic debris in the rods has become viciously radioactive. According to Sticpewich, a person standing three feet away from an unshielded assembly of spent fuel rods would receive a lethal dose in three seconds. Many of the worst gamma ray emitters decay within a few hundred years. Other constituents remain dangerously radioactive for hundreds of thousands of years. That’s a long time to stand guard over storage casks.

Spent fuel still contains fissile —chain-reacting—isotopes of uranium, plutonium, and other heavy elements. The chemical separation of these from the bits and pieces of broken atoms to make fresh fuel is called reprocessing. Because the classic method also produces bomb-grade plutonium, the United States frowns on North Korea and other countries that attempt it. Due to concerns that reprocessing here might hasten nuclear proliferation abroad, the US ended attempts at commercial reprocessing in 1976.

Elsewhere, reprocessing continued. As the UK has discovered at its Sellafield complex, the enterprise can carry high environmental costs. It is also monetarily expensive. In May of this year, French reprocessor AREVA inked a deal with the Italian government to reprocess 235 tons of spent fuel for 250 million euros.  Converted to US dollars, this is more than $1.4 million per ton. Frank von Hippel, co-director of Princeton's Program on Science and Global Security estimates a price tag of $100 billion to reprocess the existing US inventory of this commercial high-level radioactive waste.

Despite the drawbacks, reprocessing remains national policy in France, Japan, India, Russia, and the UK. The Bush administration claims that newer reprocessing technologies carry less risk of plutonium falling into the wrong hands. Large scale reprocessing would address power company demands to be relieved of the nearly 60,000 tons of spent fuel littering their grounds and put off the thorny question of permanent storage. Yucca Mountain in Nevada was supposed to serve as a permanent underground spent fuel repository, but objections from the State of Nevada, Native Americans, and environmental groups have stalled the development of the facility.

Spokespeople from the Department of Energy (DOE) chose not to speculate for me on the capacity of the proposed GNEP reprocessing plant. A facility large enough to put a dent in our national backlog of spent fuel would dwarf any existing reprocessing operation. Richard Garvin, nuclear physicist and military technology advisor to several presidential administrations, has written that the GNEP plant would be designed to handle 2,500 tons/year, only slightly more than the 2,250 tons annually produced by US commercial reactors. Even so, if he’s correct, a reprocessing facility capable of this volume would single-handedly double the amount of spent fuel reprocessed worldwide.

On the Road
Regardless of the reprocessing site chosen, spent fuel would have to travel to get there. The DOE is now soliciting proposals for a new containment device to move and store it. The Transportation, Aging and Disposal Canister (TAD canister) is supposed to provide storage space for a specific number of spent fuel assemblies. Special encasements, or overpacks, for TAD canisters will allow them to serve triple duty: transportation, above ground storage, and permanent entombment. Preliminary size specifications for a TAD canister in its transportation overpack call for a dumbbell-shaped behemoth 27’ 9” in length and 10’ 6” wide at the dumbbell ends. Filled with spent fuel, this unit would weigh 250,000 lb., equivalent to a loaded railroad coal car. On the highway, the gross vehicular weight of a TAD transport would likely tip weigh station scales at about 300,000 lb. This scoffs at the usual 80,000 lb. maximum gross weight for tractor trailers but doesn’t win any tonnage prize according to a weigh station officer with whom I spoke. He routinely sees comparable weights for rigs carrying industrial steel dies. The heaviest vehicle he recalls weighed 495,000 lb. It’s enough to make an overpass squeal for its momma.

More than a TAD
The transportation angle is what interested Sticpewich. To look into it, he accessed a 2003 DOE database containing reports from nuclear plant operators about the quantity of spent fuel held at plant sites and the rate at which each reactor produces spent fuel.

He was also granted access to TRAGIS, a software package developed by the National Transport Research Center at Oak Ridge Laboratories. Shipping dispatchers can use TRAGIS to determine highway, rail, or water routes for a variety of cargoes, including “special conditions” cargoes such as spent nuclear fuel. A dispatcher need only choose between highway, rail, or water and key in the shipment’s origin and destination. TRAGIS responds with a preferred route and alternates if desired.

After months of labor, virtual spent-fuel dispatcher Sticpewich had gleaned a trove of information on the spent fuel stored at the 48 nuclear power station sites in the northeastern quadrant of the United States. (All states east of the Mississippi and north of South Carolina) Together, in 2002, these sites were home to 30,814 tons of waste contained in 111,249 fuel rod assemblies. He calculated the number of TAD canisters required to move the entire stock of spent fuel from each plant site to South Carolina and asked TRAGIS for road, rail, and water (barge) maps of the primary and first alternate routes. His report of the project, More than a TAD: A Study of the Problems With the Transport and Reprocessing of Nuclear Waste in the Carolinas, includes an overview of GNEP, TAD canisters, specific site tonnages, and 38 state-by-state TRAGIS route maps.

“There’s a funnel effect of stuff coming down,” Sticpewich says. “It’s not very good for those of us in the South.” Asheville (I-40 and I-26) figures in several of the highway route maps. Surprisingly, the Norfolk-Southern rail line through town doesn’t appear at all. Atlanta, Charlotte, and Fayetteville would see heavy spent fuel traffic, but the biggest loser is Columbia, SC. Almost all highway and many rail routes converge there.   

Sticpewich notes that TRAGIS considers only currently authorized highways. I-240 is not among them. He believes that the completion of the I-26 connecter may result in some spent fuel shipments approaching the Carolinas on I-81 being rerouted from I-77 (through Charlotte) to I-26 (Asheville) for the direct dive south.

The Horror, the Horror
Sticpewich’s discomfort with GNEP derives from several sources. While he doesn’t rule out the possibility that research may one day enable the reliable and safe destruction of spent fuel in reactors using new technologies, he questions the wisdom of digging our spent fuel hole deeper now by building more conventional nuclear plants. Nor is he impressed by the track record of the proposed advanced burner or “fast neutron” reactors GNEP touts as a means of “burning” a higher percentage of fissionable elements. (A higher burn percentage would reduce the quantities of high-level radioactive waste requiring secure storage for hundreds or thousands of years.)

Advanced burners operate at much higher temperatures than the boiling or pressurized water nuclear reactors used here today. Liquid sodium or lead, rather than water, is usually circulated around the rods in the reactor core. Twenty-odd fast burner plants have been attempted worldwide. High costs and fires have been a problem. Japan lost the use of its new Monju reactor in 1995 when a sodium coolant pipe broke. The fire burned at 1500° C and melted the steel structures in the room. Monju is now being restarted. Apart from it and the power plants of some Russian submarines, only three fast neutron plants apparently remain in operation: the BN 600 in Russia and two small research reactors, Phénix in France and Joyo in Japan.

The vulnerability of spent fuel casks to terrorist attack also concerns Sticpewich. TAD canister design specifications call for the dry storage overpack version to withstand a direct hit by an F-15 fighter jet crash. But transportation overpack requirements fail to mention resistance to predictable terrorist methods. In response to a Congressional request for a study on the security of spent fuel, the National Research Council produced a classified report. A public version, Safety and Security of Commercial Spent Nuclear Fuel Storage, was released in 2006.The authors conclude, “It would be hard for terrorists to steal enough spent fuel from storage facilities for use in significant radiological dispersal devices (dirty bombs).”

With a droll sense of humor, Sticpewich replies, “Right. We’ll fix that by transporting [spent fuel] around.” Each TAD canister would contain 8.4 - 9.9 tons of spent fuel, including heavy quantities of gamma ray emitting fission decay products. Terrorists could not cause a nuclear explosion in a TAD, but Sticpewich’s calculations indicate that, in addition to the gamma ray emitters, each canister would contain more U-235 than the Hiroshima bomb and ten times more Pu-239 than “Fat Man,” the bomb that leveled Nagasaki. If dispersed, “dirty” may be an inadequate word to characterize the devastation wrought by such quantities of high-level radioactive waste.

Sticpewich summarizes by asking readers of More than a TAD not to accept the rationality of GNEP at face value. Rather than prescribe solutions, his report poses questions about the premises, potential benefits, and costs of GNEP proposals. He hopes readers will draw their own conclusions about what makes sense and what does not. “These questions,” he writes, “are too important to be left to the politicians and corporations.”

—Michael Hopping
copyright © 2007 all rights reserved





http://news.bbc.co.uk/1/hi/uk/709189.stm
Is nuclear reprocessing a spent force?

The British nuclear industry is in trouble with the Japanese over a disputed fuel shipment - now 7,000 jobs and the future of reprocessing is on the line.

By BBC News Online's Ryan Dilley

British Nuclear Fuels claims to be the place "where science never sleeps", but its controversial nuclear reprocessing business could soon be abruptly put to bed forever.

The possible return of British mixed oxide (Mox) fuel rods from Japan, following a furore over the safety documentation accompanying them, may spell its doom.

BNFL's Thorp plant at Sellafield in Cumbria is one of only two reprocessing facilities in the world. Its work represents around a quarter of the company's business.
Thorp Reprocessing Plant, Sellafield
Thorp's closure could see 7,000 job losses

The activity directly supports some 7,000 jobs in a remote area heavily reliant on BNFL's presence.

The plant takes spent uranium fuel rods, removes impurities and recombines the uranium with plutonium, which is also produced during reprocessing, making Mox fuel to be used again in nuclear reactors.

Mox has long been portrayed as the saviour of the nuclear energy industry. By recycling uranium, it allays public qualms about waste storage and offers nations a buffer against price hikes in, once costly, uranium.

Out of reach

Throwing plutonium back into the mix is one way of putting the weapons-grade material to a non-military use, preventing its needless stockpiling in nations such as Germany and Japan.

Mox has also been put forward as a solution to it falling into the hands of pariah states with nuclear ambitions.

Its detractors have seen reprocessing as at best an expensive "utopian" dream.

One of its fiercest critics, St Andrews University international relations professor William Walker, says the whole system has been kept afloat by political will rather than economic sense.

The disputed Japanese Mox shipment may finally sink the boat.

"Reprocessing will come to a grinding halt pretty soon," says Professor Walker.

The six-gram pellets, each containing as much energy as a tonne of coal, inside Mox fuel rods are supposed to be measured manually.

False hope

The Japanese say that in a shipment last year, the records of these tests were falsified, and want BNFL to take the rods back, even if they aren't necessarily faulty.

The Swiss nuclear watchdog spotted "anomalies" in the records of another BNFL consignment which was loaded into a reactor without mishap.
Anti-Mox demo in Japan
Opinion in Japan is turning against Mox

The breaches of "quality assurance", compounded by a lukewarm safety report on Sellafield by the Nuclear Installations Inspectorate, have seen Japan, Switzerland and Germany suspend Mox imports from the UK.

More than two-thirds of BNFL's £12bn reprocessing business comes from foreign customers, mostly Japan.

The public company even built a new £300m plant, now mothballed, on the promise of more work from its star Asian client.

Rethinking Mox

Professor Walker says the troubled fuel rods sitting at the Takahama nuclear plant, which Japan wants shipped back, have given all BNFL's customers a chance to rethink their approach to Mox.

"Japan's game plan is to put a few spanners in the works, make life difficult for BNFL and the British government to get a change of policy," says Professor Walker.



Reprocessing will come to a grinding halt pretty soon

Professor William Walker
Mox and nuclear reprocessing seem to have had their day as far as the newly liberalised foreign utility companies which make up the bulk of BNFL's customers are concerned, says Dr Gordon MacKerron of the Science Policy Research Unit.

"Japan is looking for an excuse not to take Mox because it's expensive. This may be part of an opportunistic desire to get out."

Dr MacKerron says that even if BNFL gets the spent fuel for "free", the total cost of fabricating Mox exceeds that of buying new uranium.

Locked away

Reprocessing also raises nuclear proliferation issues. The plutonium it creates, even once put into Mox, is more accessible for misuse than if left locked inside spent fuel.

Governments outside the reprocessing loop, and those on the route of ships taking Mox back from Sellafield, remain unconvinced by the scheme.
BNFL's Pacific Pintail
Ship comes in: BNFL's Mox programme may run aground

Despite tight international guidelines covering vessel safety, these ships will never be completely invulnerable to accidents, says Trevor Blakley, chief executive of the Royal Institute of Naval Architects.

"You can minimise the consequences of an unexpected event, but double bottoms and enhanced stability cannot stop your ship hitting something or something hitting you."

There is also the worry, perhaps remote, that those illegally seeking plutonium for weapons production may be tempted by Mox.

Even if terrorists or the Far East's increasingly brazen pirates give BNFL's armed ships a wide berth, environmentalists may find such a high-profile target too tempting.

Turning tide

The public mood is also turning against Mox. In Japan's Wakasa Bay, home to Takahama and 14 other nuclear plants, 2,000 locals have signed a petition querying the entire policy.

Professor Walker says Japan may now push to renegotiate its old contracts with BNFL, hoping Sellafield will agree to store rather than reprocess the country's nuclear waste.

Politically, this would be a big step for the UK authorities.

Taking irradiated material from abroad to be turned into Mox and then re-exported is one thing, keeping spent fuel in this country until a solution can be found for disposal is quite another.
Nuclear fuel protective flask
Could Britain become a nuclear storage site?

As well as trying to convince the British public of the merits of waste storage and explaining away BNFL's long commitment to Mox, the closure of Thorp could stir up a storm with its disruption to Cumbria's economy.

A closed plant would also be left with a 50-tonne inventory of plutonium, the world's largest civilian stock.

Although BNFL's new broom, Norman Askew, says it won't "walk away" from its reprocessing investment, the Japanese saga may have made that a fait accompli.

If Kansai Electric Power, and its equivalents in Germany and Switzerland, turn away from Mox, Dr MacKerron doubts Thorp or the new BNFL plant will find new business.

Market forces

"The chances of finding a decent-sized market after all these safety scares seems slim."

He also says customers "would be crazy to volunteer for plutonium" if they hadn't already entered the reprocessing loop.

Turning BNFL into a storage business may prove the financial saving of the company, says Professor Walker.

The chances of [BNFL] finding a decent-sized market after all these safety scares seems slim

Dr Gordon MacKerron

"Storage is a more viable activity. It offers stable and predictable profits. I think the British public will stomach it if the terms and safety issues are addressed correctly."

In the long term, this solution may satisfy all parties, even the environmentalists who decry the transport of spent fuel and Mox across the globe.

The economic arguments for storage may even save government plans to partially sell-off BNFL, a move shelved since the Mox fiasco.

In the short-term, the public-owned company may well end up having to foot the shipping and storage bills for the Takahama Mox, despite the fact the original fuel wasn't even produced in the UK.















http://www.ieer.org/sdafiles/vol_9/9-2/charpin.html


IEER | SDA V9N2 / E&S #16


French Report Doubts Merits of Reprocessing and MOX

by Annie Makhijani


Nuclear proponents like to point to France as the success story of nuclear energy. Nuclear power plants generate 75 to 80 percent of France's electricity and this is often held up as a symbol of the presumed wide acceptance of nuclear energy among the French public.1 However, since the late 1980s, when the French government first tried to start local investigations for possible repository sites, one of the public's top concerns has been the management of nuclear waste. This concern has, in turn, fueled a debate regarding the phase-out of nuclear power. Within this context the more narrow, but crucial, debate of putting and end to reprocessing has for the first time received official consideration.

A July 2000 report, entitled Etude économique prospective de la filière électrique nucléaire ("The Economic Prospects of the Nuclear Electricity Sector"), was commissioned by the French Prime Minister, Lionel Jospin, to provide the government2 with an economic analysis of nuclear power, including reprocessing and the use of MOX (mixed [plutonium and uranium] oxide) fuel.3 The report is known as the Charpin report, after its primary author, Jean-Michel Charpin, who is the head of the Commissariat du Plan.4 The other two co-authors are Benjamin Dessus, Director of the ECODEV (Ecodéveloppement) program at the Centre National de Recherche Scientifique,5 and René Pellat, Haut Commissaire à l'énergie atomique (Commissioner of the Atomic Energy Commission).

Given the diverse constituencies represented by the authors, including the French nuclear establishment, the report must be viewed as something of an official technical consensus document. In the introduction of the report, the authors state that:

"We did not try to define the most desirable outcomes, even less how to get there. Therefore, this study does not make any recommendation. [...] Our ambition was not to guide the choices of the authorities, or even to influence public opinion. It was to allow the necessary democratic debate to take place on the basis of verified information and explicit technical, economic and environmental reasoning."

Although the report did not make any recommendations, its two main conclusions regarding reprocessing are clear. They are, moreover, based on data furnished by the nuclear industry itself. First, reprocessing and MOX fuel use are uneconomical and will remain so for the foreseeable future. Second, reprocessing and MOX fuel use will contribute little to the reduction of the inventory of the transuranic radionuclides in waste, including plutonium.

The report is structured to show a comparative economic analysis of possible various modes of electricity generation. It also evaluates the long-term impact of those options on the environment, notably carbon dioxide emissions. What follows is a summary of Chapter I of the report, "Pour la France: l'héritage du passé" ("Regarding France: the legacy of the past"), in which the two conclusions regarding reprocessing are reached. In order to put the report in context, we first provide a quick overview of the electricity sector and MOX fuel use in France.

Electricity production in France

The overall electricity production in France in 1997 was 481 TWh (terawatt-hours)6, with 376 TWh (78 percent) coming from the nuclear sector. The civilian nuclear sector is comprised of 58 pressurized water reactors. Of these, 20 are currently using MOX, 8 can be modified to use MOX but are not presently using it, and the remaining 30 reactors use UO2 (uranium dioxide) fuel and cannot be modified to use MOX.

The reactors that are loaded with MOX use a 30 percent MOX core. The rest of the fuel is low enriched uranium. The MOX load of these 20 reactors is comprised of almost all the plutonium that is separated from French spent fuel. Table 1 shows the total amount of spent fuel unloaded from French reactors and the amount of that which is reprocessed. Were MOX to be loaded into all twenty-eight reactors that can use it, all of the approximately 1,100 metric tons of UO2 spent fuel generated annually in France could be reprocessed. There is, however, a considerable backlog of unused separated plutonium that is stored in France, since the extensive use of MOX is far more recent than commercial reprocessing.

Table 1: Types and Amount of Fuel Reprocessed in France

Type of spent fuel

Annual unloading, in metric tons

Amount reprocessed, in metric tons

UO2

~ 1100

850

MOX

~ 100

0

Total

1200

850

Source: Commission Nationale d'Evaluation Relative aux recherches sur la gestion des déchets radioactifs, Instituée par la loi 91-1381 du 30 décembre 1991, Rapport d'Evaluation No4, October 1998.

The scenarios

The report did its analysis by constructing seven scenarios. Six of these postulate various future levels of reprocessing and MOX fuel use. These are basically divided into two sets of three scenarios each, which differ only in the assumed life for the reactors (41 versus 45 years). The seventh, called S7, is a fictitious scenario that estimates the price of electricity in France assuming that reprocessing had never been initiated.

The difference in the assumed average lifetime is so small that we focus discussion here only on the second set, S4 through S6, which assume a reactor lifetime of 45 years. This is the assumption also made in the no-reprocessing scenario and therefore allows a comparison of the costs of various levels of reprocessing with no reprocessing.

Scenarios S4 through S6 involve the following assumptions:

  • Scenario S4 assumes that reprocessing would stop in 2010.
  • S5 corresponds to the current situation in France, in which 70% of the spent fuel is reprocessed and the extracted plutonium is fabricated into MOX and irradiated in 20 reactors.
  • S6 corresponds to the situation where all newly generated spent fuel (but not the past stocks of the unreprocessed spent fuel) is reprocessed and the extracted plutonium is fabricated into MOX and irradiated in 28 reactors.

Note that no scenario assumes an early halt to reprocessing. The report notes that before rejecting it, the authors had contemplated a scenario involving the termination of reprocessing in 2001, date for the renewing of Electricité de France's reprocessing contracts. The rational given for not considering an early halt to reprocessing is that a sudden stop would entail numerous technical (storage of irradiated fuel), social, and legal problems. Roland Lagarde, who is Environment Minister Dominique Voynet's point person on this, has recently broached the possibility of ending reprocessing in 2002.

Economic analysis

Table 2 summarizes the costs of scenarios S4 to S7, where the same 45-year lifetime per reactor is assumed. The costs shown include deferred decommissioning costs. (Immediate decommissioning is more expensive.) All cost figures are in constant 1999 French francs.

Table 2: Electricity Cost and Generation Under Different Reprocessing Schemes in France

Scenario

S4 (end reprocessing in 2010)

S5 (70 % reprocessing)

S6 (full reprocessing)

S7 (no reprocessing)

Cumulative cost, billions of francs

2,888

2,910

2,927

2,762

Total cumulative electricity generation, billion kilowatt-hour (billion kWh)

20,238

20,238

20,238

20,238

Average cost of electricity, in centimes/kWh

14.27

14.38

14.46

13.65

Notes: The dollar-franc exchange rates fluctuate. An approximate conversion may be made by assuming one US dollar is approximately equal to one euro. The euro and franc have a fixed relationship at 1 euro = 6.55 francs. One centime = 0.15 cents.

Several conclusions can be drawn from these results. It is clear that France would have been far better off economically without reprocessing. The cumulative cost difference between the nuclear establishment's desire for full reprocessing and no reprocessing amounts to 165 billion francs (about $25 billion, assuming 6.55 francs = one US dollar). This amounts to a difference of about 3.7 billion francs per year (about $560 million), averaged out over the entire assumed life (45 years) of all the reactors. However, MOX is used in only some reactors and for only a portion of the life of these reactors. Hence, the cost difference between the full reprocessing and no reprocessing scenarios per reactor using MOX per year of MOX use is roughly $50 million (including the related reprocessing costs).

Stopping reprocessing in 2010 would save almost 40 billion francs cumulatively ($6 billion) whereas increasing the plutonium reuse from 70 to 100% of the UO2 spent fuel generated annually would cost an extra 17 billion francs ($2.6 billion). Unfortunately, the figures for stopping reprocessing in 2001 or 2002 are not given. But an extrapolation from the figures given indicates that the savings would be considerably higher.

Material balance analysis

Table 3 shows the projected stocks of plutonium and americium at the end of reactor operating lifetimes, assumed to be 45 years, in metric tons.

Table 3: Quantities of Plutonium and Americium Contained in Unreprocessed Spent Fuel (UO2 and MOX) Generated Under Various Reprocessing Schemes in France

Scenario

S4

(End reprocessing in 2010)

S5

(70% reprocessing)

S6

(full reprocessing)

S7

(no reprocessing)

Final stock of plutonium and americium, in metric tons

602

555

514

667

Note: Americium contributes only a few percent to the quantities listed.

Hence maximum reprocessing compared to no reprocessing reduces the plutonium stock by only 153 metric tons (S6 versus S7), or only about 23%. The difference in plutonium stock between phasing out reprocessing by 2010 and full reprocessing is even smaller (15%). The reasons that reprocessing has only small impacts on plutonium stocks are:

  • Spent MOX fuel still contains a large amount of residual plutonium.
  • France has a backlog of separated plutonium from the long period when it had no reactors or few reactors using MOX. 7 France does not have the reactor capacity to use this backlog. Moreover, aged plutonium contains americium-241, a strong gamma emitter resulting from the decay of plutonium-241. Its presence is a hazard to workers and would necessitate its removal from the plutonium prior to MOX fabrication.
  • France's plan to use large amounts of plutonium in breeder reactors has fallen apart because of the severe technical problems and the very high costs of the breeder reactor program. France has permanently shut down its star of this program, the Superphénix, by far the largest breeder reactor in the world, well ahead of the original schedule.
  • There is plutonium in the spent fuel that France does not plan to reprocess, because it could not use the plutonium without engaging in a transmutation program.8

IEER conclusions

The Charpin report provides the public with first detailed look at the official data on reprocessing and MOX fuel use in France. Its conclusions clearly point the way towards an early end to reprocessing since no significant problem in the energy or waste management sectors can be addressed by it. A rapid phase-out of reprocessing and therefore MOX fuel use would appear to be in the economic interest of Electricité de France, which, like utilities elsewhere, is facing an era of deregulation and competition. The company that would be opposed to such a policy would be Cogéma, the primarily government owned company which operates all of France's reprocessing and MOX fuel fabrication plants.


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February 2001


Endnotes:

1 See, for example, Frontline documentary, "Nuclear Reaction" aired on PBS on April 15, 1997.

2 The current French government is a coalition of five left-leaning parties, including the Socialist and Green Parties. The Environment Ministry is headed by a Green Party member, Dominique Voynet.

3 Jean-Michel Charpin , Benjamin Dessus and René Pellat, Étude économique propective de la filière électrique nucléaire, La Documentation française, July 2000. This report can be found on the web in French at http://www.plan.gouv.fr/publications/4pageappert.htm.

4 The Commissariat du Plan reports to the Prime Minister. Its mission is to help guide public choices on economic and social issues by producing expert studies.

5 The CNRS is government-affiliated, and has branches in various regions of France. It conducts research in many fields, including physical and biological sciences, health, as well as economics and social sciences.

6 One terawatt is one trillion watts (1012 or 1,000,000,000,000 watts).

7 At the end of 1996, this backlog was approximately 35 tons. If foreign plutonium is included, the figure increases to about 65 tons.

8 IEER's analysis of transmutation as a waste management method -- including environmental, waste management, cost, and proliferation concerns -- is summarized in Science for Democratic Action, vol. 8 no. 3 (May 2000), on the web at: http://www.ieer.org/sdafiles/vol_8/8-3/transm.html.



http://www.nytimes.com/2005/05/12/international/asia/12korea.html?pagewanted=2&_r=1&adxnnl=1&adxnnlx=1225532759-ZbeA3tYLzKKalLjFn7skIw

North Koreans Claim to Extract Fuel for Nuclear Weapons

By JAMES BROOKE
Published: May 12, 2005

TOKYO, Thursday, May 12 - North Korea said Wednesday that it had harvested a nuclear reactor for weapons fuel, the country's latest effort to put pressure on the Bush administration and its allies.

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Space Imaging Asia

North Korea said Wednesday that it had taken spent fuel rods from a reactor at its Yongbyon nuclear complex.

Multimedia

But intelligence and Pentagon officials said that as of late Wednesday they had seen no evidence to confirm or disprove the assertion. Outside experts expressed skepticism that North Korea's action, even if confirmed, would significantly increase its weapons stockpile.

In a statement, North Korea said it had removed 8,000 spent fuel rods from a reactor at its main nuclear complex at Yongbyon as one of several "necessary measures" to bolster its nuclear arsenal.

In the worst case, experts have said, by removing and reprocessing the fuel rods, North Korea could produce fuel-grade plutonium for one to three nuclear weapons. But their suspicions were aroused because by leaving the rods inside the reactor for another year, North Korea could have obtained a much better yield of weapons fuel.

"There is a lot of symbolism and taunting here," one senior administration official said.

North Korea expelled international inspectors in late 2002, and without them, it is impossible to independently verify its claims. Both outside analysts and administration officials note that North Korean leaders could be bluffing in an attempt to wrest concessions from the United States in long-stalled six-nation negotiations to persuade North Korea to abandon its nuclear program.

Or, they said, the North Koreans could have pulled the fuel from the reactor early because of technical problems, or because of fears that the United States would order a strike on the reactor, a step that President Bill Clinton considered in 1994, during a previous crisis.

The shutdown of the reactor about a month ago, and Wednesday's statement, appear to be part of a North Korean effort to convince the world that it is already a nuclear weapons state, capable of both producing weapons and supplying itself with weapons-grade plutonium. On Thursday, Vice Minister of Unification Rhee Bong-Jo of South Korea said the reactor was closed March 31.

North Korea declared for the first time on Feb. 10 that it possessed nuclear weapons. The five-megawatt reactor at Yongbyon, the country's tightly guarded nuclear complex, was probably shut in early April, intelligence analysts said, based on satellite photos. By late last month a debate broke out in the American intelligence agencies over whether the shutdown was prompted by a need to perform maintenance, or a move to pull the rods out. Last week, two officials, one American and one foreign, reported that a platform and large crates were seen near the reactor.

"They gave me the impression that the unloading had started," Selig S. Harrison, a North Korea specialist and the director of the Asia program at the Center for International Policy in Washington, said by telephone Wednesday of meetings he had with North Korean officials in Pyongyang, the capital, from April 5 to 9.

Rods can be safely removed from a reactor shortly after a shutdown, nuclear experts said. But then they need to be cooled. After that they need to go through a complex process called "reprocessing" to extract weapons-grade plutonium.

Over the next 18 months, North Korea could produce fuel for one to three bombs from the rods, according to Daniel A. Pinkston, director of the East Asia Nonproliferation Program of the Monterey Institute of International Studies.

Removing rods and storing them in water tanks in a building adjacent to the reactor takes about six weeks, Dr. Pinkston said by telephone from California. But it would take at least six months for the rods to cool sufficiently for safe reprocessing. Reprocessing 110 tons of rods from the reactor core would take another year, he estimated.

In an interview in Washington on Wednesday, Robert Alvarez, a former senior policy adviser to the Department of Energy who visited the reactor in North Korea 11 years ago, cautioned against racing to the conclusion that North Korea was capable of making the fuel into weapons.

Thom Shanker and David E. Sanger contributed reporting from Washington for this article.





http://www.armscontrolcenter.org/policy/nonproliferation/articles/nuclear_fuel_recycling/

Nuclear Fuel Recycling: More Trouble Than It's Worth

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This article was published by Scientific American Magazine on April 28, 2008.

Plans are afoot to reuse spent reactor fuel in the U.S. But the advantages of the scheme pale in comparison with its dangers

By Frank N. von Hippel

Although a dozen years have elapsed since any new nuclear power reactor has come online in the U.S., there are now stirrings of a nuclear renaissance. The incentives are certainly in place: the costs of natural gas and oil have skyrocketed; the public increasingly objects to the greenhouse gas emissions from burning fossil fuels; and the federal government has offered up to $8 billion in subsidies and insurance against delays in licensing (with new laws to streamline the process) and $18.5 billion in loan guarantees. What more could the moribund nuclear power industry possibly want?

Just one thing: a place to ship its used reactor fuel. Indeed, the lack of a disposal site remains a dark cloud hanging over the entire enterprise. The projected opening of a federal waste storage repository in Yucca Mountain in Nevada (now anticipated for 2017 at the earliest) has already slipped by two decades, and the cooling pools holding spent fuel at the nation’s nuclear power plants are running out of space.

Most nuclear utilities are therefore beginning to store older spent fuel on dry ground in huge casks, each typically containing 10 tons of waste. Every year a 1,000-megawatt reactor discharges enough fuel to fill two of these casks, each costing about $1 million. But that is not all the industry is doing. U.S. nuclear utilities are suing the federal government, because they would not have incurred such expenses had the U.S. Department of Energy opened the Yucca Mountain repository in 1998 as originally planned. As a result, the government is paying for the casks and associated infrastructure and operations—a bill that is running about $300 million a year.

Under pressure to start moving the fuel off the sites, the DOE has returned to an idea that it abandoned in the 1970s—to “reprocess” the spent fuel chemically, separating the different elements so that some can be reused. Vast reprocessing plants have been running in France and the U.K. for more than a decade, and Japan began to operate its own $20-billion facility in 2006. So this strategy is not without precedent. But, as I discuss below, reprocessing is an expensive and dangerous road to take.

The Element from Hell Grasping my reasons for rejecting nuclear fuel reprocessing requires nothing more than a rudimentary understanding of the nuclear fuel cycle and a dollop of common sense. Power reactors generate heat—which makes steam to turn electricity-generating turbines—by maintaining a nuclear chain reaction that splits (or “fissions”) atoms. Most of the time the fuel is uranium, artificially enriched so that 4 to 5 percent is the chain-reacting isotope uranium 235; virtually all the rest is uranium 238. At an enrichment of only 5 percent, stolen reactor fuel cannot be used to construct an illicit atom bomb.

In the reactor, some of the uranium 238 absorbs a neutron and becomes plutonium 239, which is also chain-reacting and can in principle be partially “burned” if it is extracted and properly prepared. This approach has various drawbacks, however. One is that extraction and processing cost much more than the new fuel is worth. Another is that recycling the plutonium reduces the waste problem only minimally. Most important, the separated plutonium can readily serve to make nuclear bombs if it gets into the wrong hands; as a result, much effort has to be expended to keep it secure until it is once more a part of spent fuel.

These drawbacks become strikingly clear when one examines the experiences of the nations that have embarked on reprocessing programs. In France, the world leader in reprocessing technology, the separated plutonium (chemically combined with oxygen to form plutonium dioxide) is mixed with uranium 238 (also as an oxide) to make a “mixed oxide,” or MOX, fuel. After being used to generate more power, the spent MOX fuel still contains about 70 percent as much plutonium as when it was manufactured; however, the addition of highly radioactive fission products created inside a reactor makes this plutonium difficult to access and make into a bomb. The used MOX fuel is shipped back to the reprocessing facility for indefinite storage. Thus, France is, in effect, using reprocessing to move its problem with spent fuel from the reactor sites to the reprocessing plant.

Japan is following France’s example. The U.K. and Russia simply store their separated civilian plutonium—about 120 tons between them as of the end of 2005, enough to make 15,000 atom bombs.

Until recently, France, Russia and the U.K. earned money by reprocessing the spent fuel of other nations, such as Japan and Germany, where domestic antinuclear activists demanded that the government either show it had a solution for dealing with spent fuel or shut down its reactors. Authorities in these nations found that sending their spent fuel abroad for reprocessing was a convenient, if costly, way to deal with their nuclear wastes—at least temporarily.

With such contracts in hand, France and the U.K. were easily able to finance new plants for carrying out reprocessing. Those agreements specified, however, that the separated plutonium and any highly radioactive waste would later go back to the country of origin. Russia has recently adopted a similar policy. Hence, governments that send spent fuel abroad need eventually to arrange storage sites for the returning radioactive waste. That reality took a while to sink in, but it has now convinced almost all nations that bought foreign reprocessing services that they might as well store their spent fuel and save the reprocessing fee of about $1 million per ton (10 times the cost of dry storage casks).

So France, Russia and the U.K. have lost virtually all their foreign customers. One result is that the U.K. plans to shut down its reprocessing plants within the next few years, a move that comes with a $92-billion price tag for cleaning up the site of these facilities. In 2000 France considered the option of ending reprocessing in 2010 and concluded that doing so would reduce the cost of nuclear electricity. Making such a change, though, might also engender acrimonious debates about nuclear waste—the last thing the French nuclear establishment wants in a country that has seen relatively little antinuclear activism.

Japan is even more politically locked into reprocessing: its nuclear utilities, unlike those of the U.S., have been unable to obtain permission to expand their on-site storage. Russia today has just a single reprocessing plant, with the ability to handle the spent fuel from only 15 percent of that country’s nuclear reactors. The Soviets had intended to expand their reprocessing capabilities but abandoned those plans when their economy collapsed in the 1980s.

During the cold war, the U.S. operated reprocessing plants in Washington State and South Carolina to recover plutonium for nuclear weapons. More than half of the approximately 100 tons of plutonium that was separated in those efforts has been declared to be in excess of our national needs, and the DOE currently projects that disposing of it will cost more than $15 billion. The people who were working at the sites where this reprocessing took place are now primarily occupied with cleaning up the resulting mess, which is expected to cost around $100 billion.

In addition to those military operations, a small commercial reprocessing facility operated in upstate New York from 1966 to 1972. It separated 1.5 tons of plutonium before going bankrupt and becoming a joint federal-state cleanup venture, one projected to require about $5 billion of taxpayers’ money.

With all the problems reprocessing entailed, one might rightly ask why it was pursued at all. Part of the answer is that for years after civilian nuclear power plants were first introduced, the U.S. Atomic Energy Commission (AEC) promoted reprocessing both domestically and abroad as essential to the future of nuclear power, because the industry was worried about running out of uranium (a concern that has since abated).

But that was before the security risks of plutonium production went from theoretical to real. In 1974 India, one of the countries that the U.S. assisted in acquiring reprocessing capabilities, used its first separated plutonium to build a nuclear weapon. At about this time, the late Theodore B. Taylor, a former U.S. nuclear weapons designer, was raising an alarm about the possibility that the planned separation and recycling of thousands of tons of plutonium every year would allow terrorists to steal enough of this material to make one or more nuclear bombs.

Separated plutonium, being only weakly radioactive, is easily carried off—whereas the plutonium in spent fuel is mixed with fission products that emit lethal gamma rays. Because of its great radioactivity, spent fuel can be transported only inside casks weighing tens of tons, and its plutonium can only be recovered with great difficulty, typically behind thick shielding using sophisticated, remotely operated equipment. So unseparated plutonium in spent fuel poses a far smaller risk of ending up in the wrong hands.

Having been awakened by India to the danger of nuclear weapons proliferation through reprocessing, the Ford administration (and later the Carter administration) reexamined the AEC’s position and concluded that reprocessing was both unnecessary and uneconomic. The U.S. government therefore abandoned its plans to reprocess the spent fuel from civilian reactors and urged France and Germany to cancel contracts under which they were exporting reprocessing technology to Pakistan, South Korea and Brazil.

The Reagan administration later reversed the Ford-Carter position on domestic reprocessing, but the U.S. nuclear industry was no longer interested. It, too, had concluded that reprocessing to make use of the recovered plutonium would not be economically competitive with the existing “once-through” fueling system. Reprocessing, at least in the U.S., had reached a dead end, or so it seemed.

Rising from Nuclear Ashes The current Bush administration has recently breathed life back into the idea of reprocessing spent nuclear fuel as part of its proposal to deploy a new generation of nuclear reactors. According to this vision, transuranics (plutonium and other similarly heavy elements extracted from conventional reactor fuel) would be recycled not once but repeatedly in the new reactors to break them down through fission into lighter elements, most of which have shorter half-lives. Consequently, the amount of nuclear waste needing to be safely stored for many millennia would be reduced [see “Smarter Use of Nuclear Waste,” by William H. Hannum, Gerald E. Marsh and George S. Stanford; Scientific American, December 2005]. Some scientists view this new scheme as “technically sweet,” to borrow a phrase J. Robert Oppen­heimer once used to describe the design for the hydrogen bomb. But is it really so wise?

The proposal to recycle U.S. spent fuel in this way is not new. Indeed, in the mid-1990s the DOE asked the U.S. National Academy of Sciences (NAS) to carry out a study of this approach to reducing the amount of long-lived radioactive waste. The resulting massive report, Nuclear Wastes: Technologies for Separation and Transmutation, was very negative. The NAS panel concluded that recycling the transuranics in the first 62,000 tons of spent fuel (the amount that otherwise would have been stored in Yucca Mountain) would require “no less than $50 billion and easily could be over $100 billion”—in other words, it could well cost something like $500 for every person in the U.S. These numbers would have to be doubled to deal with the entire amount of spent fuel that existing U.S. reactors are expected to discharge during their lifetimes.

Why so expensive? Because conventional reactors could not be employed. Those use water both for cooling and for slowing down the neutrons given off when the uranium nuclei in the fuel break apart; this slowing allows the neutrons to induce other uranium 235 atoms to split, thereby sustaining a nuclear chain reaction. Feeding recycled fuel into such a reactor causes the heavier transuranics (plutonium 242, americium and curium) to accumulate. The proposed solution is a completely different type of nuclear reactor, one in which the neutrons get slowed less and are therefore able to break down these hard-to-crack atoms.

During the 1960s and 1970s the leading industrial countries, including the U.S., put the equivalent of more than 50 billion of today’s dollars into efforts to commercialize such fast-­neutron reactors, which are cooled by molten sodium rather than water. These devices were also called breeder reactors, because they were designed to generate more plutonium than they consumed and therefore could be much more efficient in using the energy in uranium. The expectation was that breeders would quickly replace conventional water-cooled reactors. But sodium-cooled reactors proved to be much more costly to build and troublesome to operate than expected, and most countries abandoned their efforts to commercialize them.

It is exactly this failed reactor type that the DOE now proposes to develop and deploy—but with its core reconfigured to be a net plutonium burner rather than a breeder. The U.S. would have to build between 40 and 75 1,000-megawatt reactors of this type to be able to break down transuranics at the rate they are being generated in the nation’s 104 conventional reactors. If each of the new sodium-cooled reactors cost $1 billion to $2 billion more than one of its water-cooled cousins of the same capacity, the federal subsidy necessary would be anywhere from $40 billion to $150 billion, in addition to the $100 billion to $200 billion required for building and operating the recycling infrastructure. Given the U.S. budget deficit, it seems unlikely that such a program would actually be carried through.

If a full-scale reprocessing plant were constructed (as the DOE until recently was proposing to do by 2020) but the sodium-cooled reactors did not get built, virtually all the separated transuranics would simply go into indefinite storage. This awkward situation is exactly what befell the U.K., where the reprocessing program, started in the 1960s, has produced about 80 tons of separated plutonium, a legacy that will cost tens of billions of dollars to dispose of safely.

Reprocessing spent fuel and then storing the separated plutonium and radioactive waste indefinitely at the reprocessing plant is not a disposal strategy. Rather it is a strategy for disaster, because it makes the separated plutonium much more vulnerable to theft. In a 1998 report the U.K.’s Royal Society (the equivalent of the NAS), commenting on the growing stockpile of civilian plutonium in that country, warned that “the chance that the stocks of plutonium might, at some stage, be accessed for illicit weapons production is of extreme concern.” In 2007 a second Royal Society report reiterated that “the status quo of continuing to stockpile a very dangerous material is not an acceptable long-term option.”

Clearly, prudence demands that plutonium should not be stored at a reprocessing facility in a form that could readily be stolen. Indeed, common sense dictates that it should not be separated at all. Until a long-term repository is available, spent reactor fuel can remain at the sites of the nuclear power plants that generated it.

Would such storage be dangerous? I would argue that keeping older fuel produced by the once-through system in dry storage casks represents a negligible addition to the existing nuclear hazard to the surrounding population. The 10 kilowatts of radioactive heat generated by the 10 tons of 20-year-old fuel packed in a dry storage cask is carried off convectively as it warms the air around it. Terrorists intent on doing harm might attempt to puncture such a cask using, say, an antitank weapon or the engine of a crashing aircraft, but under most circumstances only a small mass of radioactive fuel fragments would be scattered about a limited area. In contrast, if the coolant in the nearby reactor were cut off, its fuel would overheat and begin releasing huge quantities of vaporized fission products within minutes. And if the water were lost in a storage pool containing spent fuel, the zirconium cladding of the fuel rods would be heated up to ignition temperature within hours. Seen in this light, dry storage casks look pretty benign.

Is there enough physical room to keep them? Yes, there is plenty of space for more casks at U.S. nuclear power plants. Even the oldest operating U.S. reactors are having their licenses extended for another 20 years, and new reactors will likely be built on the same sites. So there is no reason to think that these storage areas are about to disappear. Eventually, of course, it will be necessary to remove the spent fuel and put it elsewhere, but there is no need to panic and adopt a policy of reprocessing, which would only make the situation much more dangerous and costly than it is today.

Fear and Loathing in Nevada The long-term fate of radioactive waste in the U.S. hinges on how the current impasse over Yucca Mountain is resolved. Opinion on the site is divided. The regulatory requirements are tough: the DOE has to show that the mountain will contain the waste well enough to prevent significant off-site doses for a million years.

Demonstrating safety that far into the future is not easy, but the risks from even a badly designed repository are negligible in comparison with those from a policy that would make nuclear weapons materials more accessible. From this perspective, it is difficult to understand why the danger of local radioactive pollution 100,000 or a million years hence has generated so much more political passion in the U.S. than the continuing imminent danger from nuclear weapons.

Part of the problem is the view in Nevada that the Reagan administration and Congress acted unfairly in 1987 when they cut short an objective evaluation of other candidate sites and designated Yucca Mountain as the location for the future nuclear waste repository. To overcome this perception, it may be necessary to reopen deliberations for choosing an additional site. Such a move should not be difficult. Indeed, the Nuclear Waste Policy Act of 1987 requires the secretary of energy to report to Congress by 2010 on the need for a second storage facility. Given the disastrous record of the DOE in dealing with radioactive waste, however, consideration should also be given to establishing a more specialized and less politicized agency for this purpose.

In the meantime, spent fuel can be safely stored at the reactor sites in dry casks. And even after it is placed in a geologic repository, it would remain retrievable for at least a century. So in the unlikely event that technology or economic circumstances change drastically enough that the benefits of reprocessing exceed the costs and risks, that option would still be available. But it makes no sense now to rush into an expensive and potentially catastrophic undertaking on the basis of uncertain hopes that it might reduce the long-term environmental burden from the nuclear power industry.

Editor's Note: This story was originally printed with the title "Rethinking Nuclear Fuel Recycling"




http://alsos.wlu.edu/adv_rst.aspx?query=reprocessing&selection=Keyword&source=all&results=10&keyword=reprocessing



https://www.osti.gov/opennet/document/purecov/nfsrepo.html

Plutonium Recovery from Spent Fuel Reprocessing by Nuclear Fuel Services at West Valley, New York from 1966 to 1972

Prepared by U.S. Department of Energy, February 1996


Table of Contents

Executive Summary
Purpose
Background
NFS West Valley Reprocessing Campaigns
NFS West Valley Plutonium Shipments to the AEC
NFS West Valley Plutonium Shipments to Others
Note

Executive Summary

This report provides a detailed accounting of the separated plutonium received by the U.S. Atomic Energy Commission (AEC), a predecessor to the Department of Energy (DOE), from Nuclear Fuel Services (NFS), which operated a commercial spent fuel reprocessing facility located near West Valley, New York, 35 miles south of Buffalo. The NFS facility was the first and only private plant in the U.S. to reprocess spent nuclear fuel. NFS began receiving spent nuclear fuel at West Valley in 1965, and operated the facility from 1966 to 1972 to chemically separate and recover plutonium and uranium from the fuel.

In total, the plant recovered 1926 kilograms (kg) of plutonium and shipped almost 80% of the material (1530 kg) to the AEC. The remaining plutonium, 396 kg, either was retained by the utility companies, sold to industry by the utilities, or purchased by NFS and later re-sold to industry for use in plutonium recycle operations.

Of the 1530 kg of separated plutonium received by the AEC from the NFS West Valley facility, 635 kg originated from fuel or reactors that were AEC-owned and 895 kg came from commercial power- reactor fuel. The AEC purchased the 895 kg of commercial power-reactor plutonium from the utility companies under a program named the Plutonium Credit Activity which was established by the U.S. Congress in the Atomic Energy Act of 1954.

All of the AEC-owned and -purchased plutonium was shipped as plutonium nitrate solution from NFS to the Hanford site. These shipments were made by commercial truck in accordance with applicable transportation regulations. Most of the plutonium received by the AEC from NFS was used in breeder reactor and zero-power reactor programs. To meet the isotopic and physical requirements for these programs, the NFS plutonium was blended with other plutonium and converted to either metal or oxide. The isotopic composition of the power reactor plutonium generally precluded its use in weapons production, even after blending, and there is no indication that blending occurred for that purpose.

Purpose

The purpose of this report is to provide a detailed account of the separated plutonium received by the AEC from NFS, a commercial spent fuel reprocessing facility located near West Valley, New York, 35 miles south of Buffalo. This document is part of a larger effort to respond to the Secretary of Energy's June 27, 1994, announced goal to declassify and release detailed plutonium information (See the DOE report, Plutonium: the First 50 Years, February 1996). This report is the first comprehensive look at NFS West Valley reprocessing operations and is the result of an exhaustive search of open literature, historical memoranda, and nuclear material accountability records.

Background

In 1953, the U.S. announced the Atoms for Peace Program. This program signaled a shift in U.S. policy from closely guarding all information about nuclear science to encouraging peaceful uses of nuclear energy at home and abroad. The agreements implementing this program allowed a sharing of information about industrial applications of nuclear energy, including nuclear fuel reprocessing techniques, while discouraging nuclear weapons proliferation. This change in U.S. policy set the stage for the International Atomic Energy Agency (IAEA), and the Nonproliferation Treaty (NPT).

The objective of the Atoms for Peace Program was to promote the domestic and international exploration, development, and advancement of the technology necessary to build and operate reliable, economic nuclear power plants; to provide cooperative assistance in establishing a self-sufficient nuclear power industry; and to ensure the development and use of nuclear energy in electric power production and salt water desalination.

To insure a self-sufficient, domestic commercial nuclear power industry, the AEC encouraged the transfer of nuclear fuel reprocessing from the federal government to private industry. As a result of this policy, three commercial reprocessing facilities were built in the U.S.: General Electric s Midwest Fuel Recovery Plant at Morris, Illinois; Allied General Nuclear Services (AGNS) plant at Barnwell, South Carolina; Nuclear Fuel Service's facility located near West Valley, New York.

Optimism about the future growth of the nuclear industry led the State of New York to set aside 3345 acres near West Valley, New York, and to encourage nuclear industries to locate there. Although fuel reprocessing had been practiced in the U.S. since 1944, large-scale fuel reprocessing in the U.S. had been conducted only at DOE facilities in Idaho, South Carolina, and Washington State, until NFS began operations at West Valley, NY.

The NFS West Valley facility was the first and only private plant in the U.S. to reprocess spent nuclear fuel. The NFS facility was a PUREX (Plutonium Uranium Extraction) process plant with a design capacity of 300 tons of fuel per year. The PUREX process included storing spent fuel assemblies; chopping the assembly rods; dissolving the uranium, plutonium, and radioactive products in acid; separating and storing the radioactive wastes, and separating uranium nitrate from plutonium nitrate. Two other commercial reprocessing facilities were built in the United States, but never operated.

In the spring of 1963, the AEC issued the necessary permits to NFS, a subsidiary of the W.R. Grace Company (NFS was acquired by the Getty Oil Company in 1969), to begin construction of a fuel reprocessing facility. NFS was granted a license on May 27, 1965 to receive and store fuel at its reprocessing facility in West Valley. The first shipment of fuel, from the Yankee Rowe reactor in Massachusetts, was placed in the fuel storage pool at West Valley on June 5, 1965. Government and commercially-generated fuel continued to be received at NFS until 1973. There were a total of 756 truck and rail shipments.

The AEC encouraged NFS to focus on commercial fuel reprocessing; however, the AEC guaranteed a minimum quantity of government fuel to NFS in the absence of sufficient commercial supplies. Sufficient commercial supplies were not available because there were not many operating commercial reactors during the NFS reprocessing period of 1966 to 1972. As a result, approximately 60% of the facility's supply of fuel and 33% of the plutonium came from AEC reactors. Specifically, a majority of this came from N-Reactor.

In 1972, NFS (now owned by the Getty Oil Company) halted all reprocessing operations in order to increase reprocessing capacity, and to alter the facility to meet new regulatory requirements. However, subsequent difficulties were encountered in retrofitting the facility to meet these requirements and, after four years of fruitless negotiations with federal and state regulatory authorities, NFS announced its intention to cease reprocessing operations and transfer the management and long-term storage of approximately 600,000 gallons of high-level radioactive liquids and sludges at the West Valley Site to the site's landlord, the New York State Energy Research and Development Authority. This transfer was in accordance with contractual obligations.

By 1980, the West Valley Demonstration Project Act (WVDPA) (Public Law 96-368) directed the DOE to solidify the high-level radioactive waste at West Valley to borosilicate glass, suitable for permanent storage in an approved federal repository. The WVDPA also directed the Department to decontaminate and decommission the tanks and facilities used at West Valley, and dispose of the low-level and transuranic wastes.

The West Valley Nuclear Services Company, a wholly-owned subsidiary of Westinghouse Electric Corporation, was selected in 1981 as the prime contractor for the WVDPA. West Valley Nuclear Services Company has operated the West Valley site for the U.S. Department of Energy since 1982.

NFS West Valley Reprocessing Campaigns

There were a total of 27 processing campaigns performed at West Valley, however, only the first 26 campaigns reprocessed intact reactor fuel. The last campaign involved processing liquid residues received from Nuclear Fuels Services facility in Erwin, Tennessee, generated during the fabrication of fuel for the SEFOR reactor. Table 1 provides a summary of the NFS fuel reprocessing campaigns including the amount of plutonium recovered. The material reprocessed by NFS, summarized by source in Table 2, was both government and commercially-generated. In both tables the quantities of "Plutonium Received" were based on shipper's data, i.e., theoretical calculations of plutonium produced in the reactors.

The "Recovered Plutonium" is the actual amount of plutonium recovered by NFS. The difference between the often imprecise theoretical calculations of plutonium produced in reactors versus the measurement of the amount actually recovered is called an inventory difference. When the recovered amount is larger than the received amount, the shipper may have under estimated the amount of plutonium produced in the reactor.

Other factors that contribute to the difference between received and recovered plutonium include the measurement uncertainty, process holdup, and normal operating losses/ measured discards. Normal operating losses/measured discards occur when known quantities of plutonium are intentionally removed from the inventory because they are technically or economically unrecoverable and are disposed of by approved methods. Two examples of normal operating losses are liquid discards to waste storage tanks, and solid waste packaged in drums and crates awaiting shipment to waste disposal facilities generically referred to as "burial sites." Examples of plutonium-bearing items sent to burial sites include discarded piping, spent ion exchange equipment, and contaminated laundry and shoe covers.

The AEC-owned plutonium came from the following:

The remaining fuel came from seven commercial nuclear power reactors that were owned and operated by commercial utility companies.

NFS West Valley Plutonium Shipments to the AEC

In the 1950's, commercial utilities began returning fuel to the Atomic Energy Commission under a program called the Plutonium Credit Activity. This program, established by the U.S. Congress in the Atomic Energy Act of 1954, provided "credit" for plutonium produced in commercial nuclear reactors operating on fuel purchased or leased from the AEC. Although the uranium in the civilian power reactor industry in the 1950's and early 1960's was owned by the AEC and leased to the utility companies, the plutonium produced during operation of these reactors was owned by the utility companies.

The Plutonium Credit Activity program began in 1957 and ended in 1970. The U.S. Government paid the utilities approximately $10.4 million for approximately 900 kg of plutonium. All of the plutonium purchased under this program was reprocessed at the NFS facility and shipped to the Hanford site with the exception of 2.5 kg plutonium from the Vallecitos Boiling Water Reactor that was reprocessed at the Savannah River site.

Both the AEC-owned plutonium and the plutonium purchased by the AEC under the Plutonium Credit Activity (1530 kg total) listed in Table 3, were shipped to the Hanford site as plutonium nitrate solution. The liquid shipments were by commercial truck in accordance with applicable transportation regulations.

Of the 1530 kg of separated plutonium received by the Hanford site from the NFS facility, 635 kg came from fuel or reactors that were AEC-owned, and the remaining 895 kg came from the commercial power-reactor fuel.

Most of the plutonium the AEC received from the NFS facility was used in the breeder reactor and the zero power reactor programs. To meet the isotopic and physical requirements for these programs, the NFS plutonium was blended with other plutonium and then converted to either a metal or an oxide. Even by blending, the isotopic mixture of the power reactor plutonium generally precluded its use in weapons production and there is no indication that blending for that purpose occurred.

NFS West Valley Plutonium Shipments to Others

As shown in Table 4, not all of the NFS separated power-reactor plutonium was sold to the AEC. A total of 396 kg of separated power-reactor plutonium was either retained by the utility companies, sold by the utility company to industry, or purchased by NFS and later sold for use in plutonium recycle operations. Of that total, almost 60% was shipped from the NFS West Valley facility to foreign countries for use in research or as fuel for foreign breeder-reactor programs.

Note

a. The Southwest Atomic Energy Associates consisted of seventeen U.S. investor-owned utilities, the Federal Republic of Germany, the General Electric Company, and Euratom. Euratom, the European Atomic Energy Community, is an organization that promotes the growth of nuclear power production in Europe. Its members are Belgium, France, West Germany, Italy, Luxembourg, and The Netherlands.


Table of Contents

Return to February 6, 1996, Press Conference Documents





http://www.sea-us.org.au/no2reactor/sa-pollies.html


Radioactive Wastes :

A Briefing Paper on the National Waste Dump

Introduction

There is currently a proposal for a national facility for the disposal of low-level and short-lived intermediate-level radioactive waste. This dump will be sited in a region of South Australia. Many believe that the wastes will come from hospitals and universities. However, 70% of the bulk of this waste will come from the Lucas Heights site run by the Australia Nuclear Science and Technology Organisation (ANSTO). The majority of radioactivity destined for the site will, however, be contained in the more highly radioactive long-lived intermediate level wastes - from reprocessed spent fuel and from isotope production (and possibly in spent nuclear fuel itself) - which it is planned to place in the store at the site until such time as a deep geological repository is established.

Option 1 Almost half the spent nuclear fuel currently held at Lucas Heights will be returned to the US for storage/disposal. It is proposed that the remaining fuel rods, and that produced by the proposed new reactor, will be reprocessed overseas. This process separates the unused uranium from the fission products and plutonium - which will be returned as either long-lived intermediate level waste (LLILW) or as high level waste (HLW) for storage in a facility next to the national nuclear dump site.

ANSTO had based its spent fuel management programme on sending the spent fuel to Dounreay in Scotland. As Dounreay is now no longer accepting foreign spent nuclear fuel, the only remaining option is to send the fuel to Sellafield in England or La Hague in France. Current contracts with the UK and France state that the waste returned must contain the same amount of radioactivity as that contained in the spent fuel sent for reprocessing - a curie for curie deal. Further, the preferred option for the UK and France is to send back HLW from reprocessing. However, as ANSTO claims that the government will not accept HLW, this issue remains to be resolved. It is important to note that the only significant difference between LLILW and HLW is that the latter is heat-generating. LLILW contains many of the same radioisotopes as HLW, a number of which have long half-lives e.g. Plutonium-239 (24,000 yrs), Americium-241 (433 yrs).

However, regardless of the final form of the waste returned a considerable amount of radioactivity will eventually sent back to Australia in the waste residues from reprocessing. The EIS on the proposed new reactor (pp.10.15) notes that of the current spent nuclear fuel stockpile, fifty per-cent is to be sent overseas for reprocessing.

Half of the spent fuel stockpile at a June 1998 (1425) 712

Fuel arising for the remainder of 1998, approx. 17

Fuel arising from 1999-2003 185

Total 914

The above figures show the amount which would remain to be reprocessed and from which waste would be returned. Using figures supplied by ANSTO a rough estimate of the total amount of radioactivity in the waste can be given. In 1992, ANSTO wrote that the stockpile of 1500 fuel rods had a total radioactive inventory of 3,000,000 curies, which equals approximately 2,000 curies per fuel rod. Using an equivalence figures the waste returned would contain 1,828,000 curies. Dounreay has already been sent 264 fuel rods sent for reprocessing (150 in 1963 and 114 in 1996) from which waste also has to be returned. This would give an additional 528,000 curies, adding to the inventory of radioactivity returned, giving a total of 2,356,000 curies.

In addition to this there will also be the LLILW from the production of medical and industrial isotopes at Lucas Heights which is also destined for storage. This material also contains a considerable amount of radioactivity, as well as long-lived radioisotopes. If the new reactor goes ahead the isotope production will increase four-fold, with a corresponding increase in the amount of radioactivity in the waste. There are no figures for the amount of radioactivity which would be in the spent nuclear fuel from the new reactor except that approximately the same number of fuel rods, 37 per year, would be produced over an operating period of 40 years. Ultimately the spent fuel and/or waste from the second reactor would go for storage and, in theory, then be disposed of.

Option 2: If reprocessing contracts do not eventuate for the spent nuclear fuel stockpile (and future irradiated fuel rods) they might be sent directly for storage at the national nuclear dump site. Indeed, this option has been available for some time. In 1990 the NHMRC codes for the ‘disposal’ of radioactive waste created the option for storage when Category S waste was introduced (the ultimate disposal of which is not actually covered by any codes). As the EIS notes, in the unlikely event that "the overseas option (for reprocessing) should become unavailable it would be possible at short notice to take advantage of the off-the-shelf dry storage casks for extended interim storage at the national storage facility, pending renewed arrangements being negotiated for the reprocessing/conditioning or the fuel".(p. 10.18 EIS).

ANSTO, insists, however, that the spent fuel from the current reactor has to be reprocessed or conditioned and it is not suitable for direct disposal. ANSTO has also said that the fuel for the new reactor will be designed so that it can be stored long-term, but that this too would also have to be reprocessed or conditioned prior to disposal. ANSTO have said that they are not seeking a fuel type which would be suitable for direct disposal (the US Department of Energy is currently investigating non-conditioning direct disposal of the type of spent nuclear fuel currently used by the Lucas Heights reactor).

Option 3: Send the spent nuclear fuel for storage at the dump site and condition the waste there or condition the waste at Lucas Heights and send the resulting waste to South Australia for storage. ‘Conditioning’ means partial reprocessing, that is the dissolution of the spent nuclear fuel in acid, without separation of the uranium or plutonium. Conditioning in Australia is not an entirely unrealistic scenario. In its 1996 review of radioactive waste management ANSTO outlined following plan for spent nuclear fuel:

Since 1996 the ‘conditioning’ option was explored for the spent fuel at the Lucas Heights – and was soundly rejected. The local MP is adamantly opposed to such a proposal, as are the unions representing workers on site and the local residents. Whether such reprocessing/conditioning would necessarily take place overseas, or at the national nuclear dump site now becomes the key issue. There is certainly no guarantee that the spent nuclear fuel remaining, or that which will be created, will be reprocessed overseas. In April of this year ANSTO stated it was confident that the fuel rods would be reprocessed at Dounreay – an idea that had to be abandoned only weeks later.

Political pressures are being brought to bear on both Sellafield and La Hague to clean up their operations. There is ever-increasing pressure for the actual closure of both facilities coming from political parties, environment groups and affected populations. The idea that these reprocessing plants will be operating in ten or twenty years, let alone until 2043 when the proposed new reactor will close, is something which has to be discussed now. However, if such plants are open and if they take the spent fuel there is still the long-term issue of all the radioactivity coming back – for storage at South Australia.

Disposal

In theory both HLW and LLILW should ultimately be disposed of in a deep geological repository. Many national nuclear agencies have encountered major technical and financial problems, and political opposition, when pursuing such proposals. Only last year, the UK’s nuclear waste agency, NIREX, was forced to abandon plans to site an exploratory rock laboratory near the Sellafield reprocessing plant. That decision, made by the Conservative government, came after official inquiries concluded the proposal was unsound. The normally pro-nuclear regional authority, Cumbria County Council, also rejected the scheme. Having spent 14 years searching for a deep geological repository, and having spent $430 million, a nuclear waste site could not be found even in the ‘nuclear heartland’ of West Cumbria. Quite how long the higher-level wastes will remain stored in South Australia is, therefore, open to question. A the Department of Primary Industry & Energy has noted "the small quantity of Category S waste produced by Australia cannot presently justify the cost of constructing a geological disposal facility." Would the government establish a repository for direct disposal of spent fuel? In 1995 Commonwealth Environment Protection Agency noted:

"Direct disposal in Australia (of spent fuel rods). Direct disposal of spent research reactor fuel would raise significant policy and technical problems such as operation of deep geological repositories.
ANSTO – Conflict of Interest

There is a clear conflict of interest in ANSTO acting as an adviser to the government on the matter of radioactive waste disposal. ANSTO produces the bulk of radioactive waste for the Commonwealth – a government report from 1992 shows that ANSTO held 70% of the national total of low-level waste on site at Lucas Heights. ANSTO also produces the spent nuclear fuel and isotope wastes which contain the majority of radioactivity in Commonwealth wastes. Local residents and a number of politicians have expressed their concern at Lucas Heights remaining as the de facto national nuclear dump. In 1995 the Commonwealth EPA.

" Storage at Lucas Heights. Storage at Lucas Heights of HIFAR spent fuel has been safely carried out on site for over thirty years. However, continued accumulation of spent fuel at Lucas Heights defers the problem of eventual disposal, and invites opposition from local residents and local government." (emphasis added)

It is crucial to this debate to understand the political problems of keeping spent nuclear fuel, and other wastes, at Lucas Heights - particularly at a time when a new reactor is being proposed. Government agencies recognise this, and they also know establishing a deep geologic repository for the more radioactive materials or for spent fuel will also prove problematic. What then is the likelihood of building a final disposal facility elsewhere in Australia once a store is firmly established in South Australia?

About the author: Since 1980 Jean McSorley has worked as a campaigner on the nuclear industry in Europe, Australia and Asia. She was formerly coordinator of the Nuclear & Energy campaign in Asia for Greenpeace International. She holds a Master of Policy Studies from the University of New South Wales and is author of ‘Living in the Shadow, the Story of the People of Sellafield’ (Pan books, 1990). Contact mcsorley@compassnet.com.au. Tel (h) 02 9658 3265 or mobile 0417 662 720


Many thanks to Jean McSorley for supplying this article to SEA-US Inc.
Page last updated October 31, 1998.

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http://www.tri-cityherald.com/962/story/368514.html

Nuclear fuel recycling shouldn't be shelved again

The Department of Energy's new draft environmental study on the Global Nuclear Energy Partnership looks largely to be an exercise in futility.

No matter who is elected president next week, he'll pursue his own energy strategy. Not many elements of the Bush administration's ambitious GNEP proposal are likely to survive the transition.

But GNEP's basic aim -- to develop better technology to safely reuse the nation's spent nuclear fuel -- shouldn't be abandoned.

Sure, there's no shortage of uranium needed to fuel existing reactors around the world, but that won't be true forever.

Demands are certain to increase, and supplies will eventually dwindle. If we wait for a crisis before pursuing reprocessing technology, it'll be too late.

The U.S. will run out of storage space for spent fuel long before it runs out of uranium for new fuel rods. The nation's stockpile of spent nuclear fuel is expected to exceed capacity of the proposed Yucca Mountain repository by 2010.

The potential for recycling to drastically reduce the need for new geological storage could make the technology cost effective, regardless of uranium supplies.

Arguments that commercial fuel reprocessing in the U.S. will contribute to proliferation of nuclear weapons are unconvincing.

The U.S. abandoned its reprocessing program in 1977 to set an example for the rest of the world. It hasn't worked. Other countries reprocess nuclear fuel, and the number of nations in the nuclear-weapons club continues to expand.

If anything, a U.S. program to develop proliferation-resistant technology for reprocessing spent reactor fuel promises to slow the growth in countries with nuclear weapons.

A public hearing on DOE's draft environmental statement is planned at 7 p.m. Nov. 17 at the Pasco Red Lion, 2525 N. 20th Ave. An Oregon hearing will be held the next evening in Hood River.

We suspect the comments collected will become a footnote to a DOE proposal that's shelved indefinitely come inauguration day.

But the need for nuclear energy is becoming increasingly obvious to more Americans. Just last week, the New York Times ran this headline: "The Energy Challenge -- Nuclear Power May Be in Early Stages of a Revival."

Sustaining that revival for the long haul without reprocessing in the mix won't be possible. The next administration needs to continue funding research and development.





http://books.nap.edu/openbook.php?record_id=4912&page=413

APPENDIX J
FUEL REPROCESSING ECONOMICS

INTRODUCTION

Transmutation of transuranics (TRUs) and fission products that are recovered from spent fuel offers potential for improving the technology for long-term disposal of radioactive waste. Successful implementation of this integrated reprocessing/irradiation strategy would require a major financial commitment to the development, design, construction, and operation of a series of reprocessing plants and transmutation reactors based largely on as-yet unproven technology.

This appendix addresses various economic issues related to the use of transmutation as a primary waste management strategy, focusing primarily on future reprocessing costs under various plant ownership and financing arrangements. It also addresses the substantial institutional barriers that would inhibit private-sector financing of such a strategy in the United States.

HISTORICAL PERSPECTIVE

The nuclear industry of the early 1970s was characterized by rapidly increasing worldwide demand for generating commercial nuclear power capacity, rising uranium prices, and an impending shortage of uranium enrichment capacity. There was a consensus within the nuclear community that spent reactor fuel would be reprocessed to recover residual uranium and plutonium for recycle in light-water reactors (LWRs) and ultimately to fuel breeder reactors. Projected reprocessing costs were low, and there appeared to be an urgent need to reduce the rapidly increasing demand for virgin uranium in order to stem rising prices and prepare for early introduction of breeders. U.S. enrichment capacity was sufficiently committed by 1972 that the U.S. Atomic Energy Commission (AEC) closed the books on new orders for enrichment services.

Reprocessing and uranium and plutonium recycle in LWRs was expected to reduce total fuel-cycle cost relative to a once-through fuel-management scheme. Confidence that a reduction in cost would be realized was supported by commercial contracts for reprocessing services at unit prices below $20/kgHM in the late 1960s. The initial estimates of the cost premium for MOX fuel fabrication were as little as 20% above the comparable cost of fabricating virgin uranium fuel. Spent fuel was expected to be reprocessed within approximately 6 months following discharge from the reactor, so that recovered uranium and plutonium could be returned to the reactor with minimal delay.

Through the late 1960s, the U.S. outlook for nuclear power plants and for fuel-cycle facilities to undertake commercial uranium and plutonium recycle facilities was favorable. Two commercial facilities for reprocessing LWR spent fuel were constructed. The General Electric

plant at Morris, Illinois, was completed in 1968, and the Allied-General Nuclear Services plant at Barnwell, South Carolina, was completed in 1974. However, neither plant went into commercial service.

The 20-year period of nuclear optimism began to wane in about 1970 with growing public apprehension over the possibility of a major nuclear accident. This in turn prompted criticism of the AEC, which had the dual responsibilities for developing and promoting nuclear power and for regulating its implementation in the private sector. The passage in 1970 of the National Environmental Policy Act (NEPA) fundamentally changed the ground rules for nuclear plant siting and construction. NEPA added a requirement for the preparation of an environmental impact statement for all new major facilities, with provisions for public hearings on the statement before a construction permit could be issued.

Public dissatisfaction with AEC management of nuclear issues heightened with the revelations attending the cancellation of the planned high-level waste (HLW) repository near Lyons, Kansas. The public became aware that an approved waste repository site had not yet been secured to receive the steadily increasing quantity of spent fuel, as well as HLW from defense operations. In 1974 the Ford administration divided the AEC into two new organizations that separated the responsibilities for nuclear development and regulation. The new organizations were the Energy Research and Development Administration (ERDA) and the Nuclear Regulatory Commission (NRC). At the same time, Congress disbanded the powerful Joint Committee on Atomic Energy and reassigned its responsibilities among several congressional committees.

A new public concern arose when India tested a ''peaceful nuclear explosion" in 1974, rekindling an earlier controversy over the postulated link between nuclear power and nuclear weapons proliferation. This concern was heightened by the revelation that the Indian nuclear explosive contained nuclear weapons material produced in a reactor that was sold to India by Canada. The Indian nuclear test made it necessary for many nations, including several developing countries, to acquire their own facilities to enrich uranium or recover plutonium from spent reactor fuel. The growing controversy associated with the widespread commercial use of plutonium recycle came to a head in the highly contentious hearings on the Generic Environmental Statement on Mixed Oxide (GESMO) fuel, which the NRC had begun in late 1974 and which the Carter administration finally canceled in 1977.

In 1977, the Carter administration completed a review, begun by the Ford administration, of the plans to commercialize the breeder reactor and engage in plutonium recycle in the United States. In addition to placing greater emphasis on nonproliferation concerns, this review was based on projections of the growth in electric power demand that were much lower than the earlier projections of the AEC up to the mid-1970s. This reappraisal soon led to cancellation of breeder commercialization and plutonium recycle, leaving the Barnwell reprocessing plant without an operating license or a mission.

From 1977 to 1979, the United States joined other nations in the International Fuel Cycle Evaluation to reconsider the commercial use of plutonium. The U.S. Congress passed the Nuclear Nonproliferation Treaty of 1978, which placed restraints on foreign reprocessing of nuclear fuel of U.S. origin.

Several nations took issue with the change in nuclear ground rules implemented unilaterally by the United States. However, most ultimately agreed that steps to limit reprocessing and recycle would be prudent, although they retained reprocessing as a long-term option. The International Fuel Cycle Evaluation also reached agreement that spent fuel itself was a waste form that could be safely disposed of in a waste repository. Indeed, by 1977, the United States was strongly recommending that course, which was adopted and further promoted by several other nations, notably Sweden, that had small nuclear programs. However, the European reprocessors and Japan continued their plans to reprocess spent fuel from commercial reactors and to store the separated plutonium pending further development of their breeder programs.

When the U.S. ban on domestic fuel reprocessing was lifted in the early 1980s, the previously favorable political and institutional environment for nuclear energy no longer existed, and the economic incentives for reprocessing had changed markedly. The principal factors precluding the resumption of commercial reprocessing in the United States were as follows:

These issues apply not only to centralized, large-scale reprocessing plants but also to smaller onsite reprocessing plants, transmutation reactors, and an integrated complex of reprocessing plants and transmutation reactors. Overcoming these barriers will be a formidable challenge. 

REPROCESSING-PLANT CAPITAL COSTS

While pyroprocessing technology is being considered for reprocessing spent fuel that is associated with transmutation of TRUs, this technology is not sufficiently mature that reliable reprocessing-plant capital and operating cost estimates can be prepared. Moreover, it is by no means certain that pyroprocessing will prove more economical than conventional aqueous reprocessing, for which the technology is relatively mature. While Argonne National Laboratory (ANL) prefers pyroprocessing technology, the fuel-cycle costs developed by General Electric (GE) for the ALMR program are apparently based on the cost of plutonium and uranium recovery by extraction/transuranic extraction (PUREX/TRUEX) aqueous technology for reprocessing LWR spent fuel to start and refuel ALMRs. The GE estimates are based on PUREX aqueous technology, combined with new TRUEX technology for high-yield recovery of all TRUs. The capital costs developed in this section, and the operating costs developed in the section Reprocessing-Plant Operating Costs are therefore based on aqueous reprocessing technology.

Capital Costs Associated With Reprocessing Plant Projects

Capital cost information was obtained from the open literature and private communications for three reprocessing plant projects: THORP (United Kingdom), UP3 (France), and Rokkashomura (Japan). UP3 is in operation, THORP is in the startup phase, and Rokkashomura is under construction. These three plants have annual throughputs in the range of 800 to 900 MTHM/yr, and each is based on aqueous PUREX technology.

THERMAL OXIDE REPROCESSING PLANT (THORP)

The THORP reprocessing plant, which is located at the Sellafield site in the United Kingdom, is owned by British Nuclear Fuels, plc. THORP services include fuel receipt and interim storage; reprocessing (including conversion of uranium and plutonium to oxide); HLW vitrification and intermediate storage; intermediate-level waste encapsulation, interim storage, and disposal; and low-level waste (LLW) disposal. The reprocessing-plant capital and operating costs used in this appendix are based on this scope of services.

The reported capital cost of the THORP facility ranges from £2,600 million ($4,700 million in 1992 dollars) reported by Wilkinson (1987) to £4,000 million ($6,800 million) reported by K. Uematsu (private communication, 1992). The most credible cost is £2,850 million ($4,560 million), which was reported in the July 1993 report The Economic and Commercial Justification for THORP (British Nuclear Fuel, 1993). This cost excludes interest during construction since the plant was financed through up-front payments by THORP customers.

The average annual plant throughout scheduled for the initial 10 years of operation is 700 MTHM/yr, but British Nuclear Fuel estimates that the plant can process 900 MTHM/yr (1,200-MTHM/yr capacity, with operation at a 75% capacity factor). The OECD/NEA study, which based its reprocessing plant costs on the THORP facility, assumed a plant throughput of 900 MTHM/yr as well.

UP3

UP3 is the most recent addition to the large French reprocessing complex at La Hague. It reportedly has a design capacity (annual throughout) of 800 MTHM/yr. UP3 has been in operation since 1990, providing complete services that range from spent-fuel storage through HLW vitrification.

COGEMA, the owner/operator of UP3, reported a total capital cost of ff 50 billion for UP3 plus the 400-MTHM/yr expansion of UP2 to 800 MTHM/yr. If two-thirds of the cost is allocated to UP3 (based on the ratio of plant capacities), the resulting UP3 capital cost would be approximately $5,800 million. COGEMA also reported that the design and construction of UP3 required 25 million engineering man-hours and 56 million man-hours of field construction (Reprocessing News, 1990). While no information was provided on the cost of equipment,


materials, interest during construction, and other such costs, factoring in these costs based on historical experience results in a capital cost of $6,670 million to construct a comparable facility in the United States.

ROKKASHOMURA PLANT

Japan Nuclear Fuel, Ltd. is currently constructing an 800-MTHM/yr reprocessing plant at the Rokkasho Village site. It is scheduled for operation in 2000. The technology is primarily French, with U.K. and German design input as well. This facility provides complete services, including HLW vitrification and storage for 8,200 waste canisters. The products are uranium and plutonium, with the plutonium diluted with uranium and converted to a 50/50 mixture of uranium/plutonium oxide.

Despite the lessons learned on the design and construction of the UP3 and THORP reprocessing plants, the constant dollar capital cost at Rokkashomura has not decreased significantly relative to these earlier plants. Reported capital costs for this facility range from $6,500 million (Chang, 1992) to $5,200 million (¥740 billion) (JGC, 1991). Because of the particularly stringent seismic design requirements in Japan, the cost of a facility of comparable capacity would probably be less in a region of lower seismicity.

Capital Costs Associated With Reprocessing Plant Studies

Capital costs associated with a number of studies were also evaluated, the most important being the June 1993 "final revised draft" of the OECD/NEA study The Economics of the Nuclear Fuel Cycle (OECD/NEA, 1993). The committee considers this study particularly credible, because it is based on cost data from the recently completed THORP plant and includes input from COGEMA, the owner/operator of UP3. The capital costs reported in the OECD/NEA study are shown in Table J-1.

The total estimated cost of £3,297 ($5,370) million is 15% higher than the reported actual cost of THORP of £2,850 million ($4,560 million without interest during construction). The reason for this cost difference is not evident, but it could be associated with the higher cost of construction at the "grass roots" site assumed in the OECD/NEA study as compared with the existing site on which THORP is located.

In addition to the above capital-cost estimates for actual plants and the OECD/NEA study, a number of other studies of reprocessing plant economics have presented estimates over the past decade. Examples include the following:

The capital costs estimated in the first two of the above studies are substantially below those experienced in the construction and operation of actual plants. This is particularly difficult to rationalize considering that the study plants include new TRUEX separations and have annual throughputs two to three times higher than THORP, UP3, and Rokkashomura. Assuming that reprocessing plant capital costs are proportional to the 0.6 power of plant capacity, scaling the Gingold estimates to a 900-MTHM/yr capacity would result in a capital cost of $2,010 million for a government-owned facility and $2,210 million for a privately owned facility. Similarly, the GEl capital cost would decrease to $3,160 million for a 900-MTHM/yr plant, less the cost of the fuel fabrication facilities included in the GE estimate. These costs are only one-third to one-half of the costs reported for actual plants of 800 to 900–MTHM/yr capacity.

Even lower estimates of capital costs were presented earlier by the ALMR project (Salerno et al., 1989) for PUREX/TRUEX reprocessing plants designed for high-recovery yield of all TRUs from LWR spent fuel. Two cost estimates were presented, one with an annual throughput of 300 MTHM and a second with an annual throughput of 2,500 MTHM. Their estimates, escalated from 1989 to 1992 dollars, were $227 million and $4,250 million, respectively. Scaling the 300-MTHM/yr plant estimate to 900 MTHM/yr would result in a cost of $440 million, while scaling the 2,700-MTHM/yr plant estimate to 900 MTHM/yr would result in a cost of $2,200 million. These estimates are far below the reported capital costs of actual plants. More important, they indicate an inverse economy of scale with plant throughput, which has not been observed or predicted in other studies.

Based on the above information, the committee concludes that reported capital costs for actual contemporary plants currently provide the most reliable basis for estimating the cost of future plants. Estimated capital costs reported in recent U.S. studies appear inexplicably low.