By: Hisham Zerriffi and Annie Makhijani
Prepared for the Institute for Energy and Environmental Research
May 2000
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One of the biggest obstacles facing the nuclear industry is what to do with the nuclear waste generated in the form of spent fuel discharged from commercial reactors or in the form of high-level waste originating from the extraction of plutonium from spent fuel.1 Most countries' preferred option for the isolation of nuclear waste from the public and the environment is to bury it underground in a deep geological repository. However, because the spent fuel and the high-level waste contain a number of radionuclides that have very long half-lives (thousands of years to millions of years) it is generally acknowledged that it is impossible to ensure the isolation of the waste for such long periods of time. Besides the likelihood of leakage of some long-lived radionuclides, it is also impossible to guarantee against human intrusion (intentional or inadvertent). The extremely difficult questions regarding ensuring isolation of waste to a degree sufficient to prevent severe contamination of resources, notably water resources, has made the siting of repositories a controversial scientific and policy issue and has been at the center of much of the public concern and opposition to repositories. Further, the political expediency that has frequently accompanied the selection of sites for study has intensified this opposition. While programs for siting repositories for spent fuel and high level waste are in various stages in different parts of the world, these still face immense scientific hurdles and intense public opposition. In the United States, which has a 2010 target date for opening a repository, there are still no final environmental standards for the protection of the health of future generations and of the environment from the proposed repository at Yucca Mountain. 2 The difficulties and questions associated with repository siting, notably the extremely long periods of isolation required, have caused some to view the transmutation of long-lived radionuclides into short-lived ones as a potential solution to the problem of radioactive waste management. Transmutation is done by inducing nuclear reactions of various types in the nuclei of long-lived radionuclides. The theory is that a transmutation program would transform the vexing problem of long-term isolation into a far less difficult one of storage for several decades or a few hundred years. This theoretical promise has led proponents of transmutation to claim that it would greatly decrease the problems associated with long-term management of nuclear waste. Occasionally, they have even claimed that it might eliminate the need for a repository, though such claims have tended to recede as investigations into the practicalities of transmutation have progressed. At the same time, environmental, waste management, cost, and proliferation concerns have risen. In addition to its promise of a solution to the nuclear waste problem, some transmutation proponents have touted it as the only complete solution to the proliferation problems posed by plutonium. They argue that as long as plutonium remains, either in stockpiles of separated plutonium or in spent fuel that can be reprocessed to obtain separated plutonium, the proliferation risks will remain. Their solution is to use the plutonium as fuel in reactors even if this requires the separation of the plutonium and therefore an increase in proliferation risks over the short term. Transmutation basics Transmutation is the transformation of a radionuclide into another radionuclide, or into two or more radionuclides. Nuclear waste transmutation involves nuclear reactions that would occur in some form of nuclear reactor (thus producing electricity at the same time as transmuting the radionuclides).3 A variety of reactor schemes have been proposed, but they all possess a common characteristic: a substantial amount of energy must be delivered to the nucleus of a long-lived radionuclide in order to induce a nuclear reaction that would convert it into a short-lived radionuclide or a stable element. Figure 1
The figure above shows the main components of an idealized transmutation system. A reprocessing plant is needed to sort out the candidate radionuclides slated for transmutation by separating certain long-lived radionuclides from the others. (In the context of transmutation, reprocessing is also called "separation" or "partitioning.") This allows the selective conversion of long-lived radionuclides into short-lived ones when they are irradiated in a reactor. Without reprocessing, the opposite kind of nuclear reactions would cause a counterproductive conversion of some short-lived radionuclides into long-lived ones. The fabrication facility then manufactures the long-lived radionuclides into fuel and/or targets that are then sent to the transmutation facility, where the conversion of the nucleus actually takes place. The central component of a transmutation facility is a nuclear reactor. It may be a critical reactor, which is a self contained transmutation device, or a sub-critical reactor, which needs an outside source of neutrons to sustain a chain reaction.4 The neutron induced reactions in the reactor transmute the long-lived fission products into short-lived ones; they also fission the actinides, such as plutonium, creating new fission products. Most of these fission products are short-lived, but new long-lived fission products are also created (see below). The actinides, like uranium and plutonium, can also absorb neutrons, resulting in the creation of higher-mass actinides (see below). So plutonium and other transuranic radionuclides are actually being created in some portions of the fuel in transmutation devices, while in others they are being destroyed. Further, not all actinides can be transmuted before the nuclear reactor becomes very inefficient. Hence, a number of passes through the reprocessing, fuel fabrication, and reactor facilities are needed in order to transmute most long-lived radionuclides. Transmutation of all long-lived radionuclides into short lived ones to a degree sufficient to obviate the need for a geologic repository is practically impossible. In particular, the transmutation of separated uranium, which constitutes about 94 percent of the weight of light water reactor spent fuel and which is very long-lived and generally contaminated with some fission products, would be counterproductive. The main transmutation route for almost all the uranium would be to convert uranium-238 (the dominant isotope) into plutonium-239. Hence, the complete transmutation of uranium-238 essentially requires the creation of a plutonium economy, which would be unsound whether viewed from an economic, environmental, or non-proliferation standpoint. Almost all the uranium must therefore be disposed of without transmutation as a matter of practical necessity. Other long-lived fission products as well as residual transuranic actinides would also need disposal. Hence, a repository, as well as other waste management and storage facilities would still be an essential part of transmutation schemes. The merits of transmutation schemes and the difficulties associated with them become clearer if we understand some basics about the physics of transmutation. The physics of transmutation Two transmutation reactions are important for nuclear waste management: neutron capture and fission.5 The goal is that long-lived radionuclides be transformed into short-lived radionuclides that then decay into stable isotopes. To provide concrete examples, this section will discuss neutron capture by two long-lived fission products: iodine-129 and cesium-135. In addition we illustrate two reactions involving plutonium-239 transmutation.6 The absorption of a neutron by iodine-129 results in the production of short-lived I-130 and then in the stable isotope xenon-130.7 Cesium-135 captures a neutron to become short-lived Cs-136, which decays into stable barium-136.8 Hence, in these two cases, nuclear theory indicates that transmutation of these troublesome long-lived radionuclides into non-radioactive, stable ones is possible. However, as a practical matter only I-129 can actually be considered a candidate for transmutation. In the case of cesium-135, transmutation would first require the separation of this specific isotope from cesium-133, which is stable. This is because successive capture of neutrons by cesium-133 converts it first into Cs-134 (short-lived) and then into Cs-135, which is long-lived.9 The cesium in spent fuel is a mixture of both Cs-133 and Cs-135 isotopes which cannot feasibly be separated, in part because the presence of the very radioactive Cs-137 isotope makes the handling and processing of the cesium extremely difficult, expensive, and dangerous. Thus, it is easy to see that the benefit of transmuting Cs-135 would be negated by the production of more Cs-135 from the neutron capture of Cs-133. Some neutrons interactions with plutonium-239 result in fission while others result in the formation of plutonium-240 with a half-life of 6,500 years, which while shorter than the 24,000-year half-life of Pu-239, is evidently still very long. Successive neutron captures result in higher plutonium isotopes.10 This illustrates that transmutation nuclear reactions would need to be closely controlled so that there is an overall change from long-lived to short-lived radionuclides without a build up of new long-lived radionuclides. Note also that neutron capture by plutonium-239 and -240 would not solve the problem of eliminating long-lived radionuclides even if all the plutonium were converted to short-lived plutonium-241. This is because plutonium-241 has an entire decay chain associated with it. It decays into americium-241, which has a half-life of 430 years. Amercium-241 in turn decays into neptunium-237, which has a half-life of over 2 million years. It is evident that neutron capture and the creation of heavier plutonium isotopes creates new problems in place of old ones. By contrast, when plutonium-239 fissions, most fission products are short-lived, while some are long-lived. Hence, significant reduction of the mass of long-lived actinides, such as plutonium, generally necessitates fission of the nuclei. Fission transmutation reactions produce mostly short-lived fission products that decay into stable elements. The example below shows the production of two short-lived fission products, tellurium and molybdenum. They both undergo a series of beta decays. The decay chain of molybdenum-102 consists of short-lived radionuclides until it reaches stable (non-radioactive) ruthenium-102. Tellurium decays into long-lived cesium-135.
Pu-239 + n ®
Pu-240 ®
Te-135 (19 seconds)
Proposed transmutation schemes Various schemes have been proposed for transmutation. Three types of reactors (light water reactors, fast reactors, and sub-critical reactors) and two types of reprocessing have been proposed. Table 1 shows the type or types of reprocessing associated with each type of reactor and the radionuclides that would be candidates for transmutation. Most transmutation schemes would use a combination of reactors and associated reprocessing technologies. For example, in one scheme, light water reactors would be fueled with mixed oxide (MOX) fuel - that is, fuel made with plutonium extracted from conventional reactor spent fuel which is mixed with depleted uranium, with both materials being in an oxide chemical form. The MOX spent fuel then would be reprocessed and the transuranic actinides would be extracted to fuel a fast neutron reactor (also commonly called a breeder reactor). The fast reactor fuel would, in turn, be reprocessed and the remaining actinides would fuel a sub-critical accelerator driven reactor.
Table 1: Transmutation schemes
None of these schemes can transmute uranium, cesium-135, carbon-14, and some other radionuclides. Table 2 (below) shows the various radionuclides of concern from the point of view of long-term management and their status with respect to various transmutation schemes.
Table 2: Main Long-lived Radionuclides of Concern
Residual Waste Even the most elaborate transmutation schemes will leave behind substantial amounts of long-lived radionuclides requiring disposal, while generating large new volumes of operating and decommissioning wastes. Transmutation does not eliminate the need for a high-level waste repository. First, no transmutation scheme is able to deal with all of the radionuclides of concern since many cannot be transmuted for practical purposes (see example of uranium and Cs-135, above). Second, transmutation of Tc-99 and I-129 is not 100% effective, even with multiple passes through the reactor. Third, new long-lived fission products are created from the fission of the actinides. Fourth, fissioning of the actinides is not 100% effective in eliminating them. For instance, even the most optimistic, best-case estimate concedes that at least 2.4 metric tons of transuranic radionuclides would be left over after the transmutation of 906 metric tons of transuranics anticipated to be produced by US nuclear reactors during their licensed lifetimes.11 Moreover, the composition of the residual transuranic waste would be shifted towards higher isotope actinides, making the residual fraction more radioactive per unit weight. This would result in greater radiological risks, complicate disposal, and limit any gains in repository capacity due to a smaller actinide inventory. Fifth, the disposal in a repository of cesium-137, which is mixed with cesium-135 in spent fuel, would necessitate a large repository. This is because the intense radioactivity of cesium-137 results in the generation of a large amount of heat, which necessitates an increase in spacing of the disposal canister. The large space requirements would negate one of the most important benefits of transmutation - that of reducing repository size for a given nuclear energy generation.12 Only storage of long-lived wastes for a hundred years or more, with its attendant high uncertainties, risks, and costs, would significantly alleviate this repository capacity problem.13 Finally, waste from prior reprocessing operations, whether for commercial or military purposes, is highly unlikely to be transmuted since almost all of it will have been vitrified for safety reasons before a transmutation program can be put into place. This large amount of waste would have to be sent directly to the repository. In other words, there are fundamental and substantial limitations to the reduction in long-lived radioactivity that can be achieved even with an elaborate and very expensive transmutation program. Table 2 shows the main long-lived radionuclides of concern and the feasibility of their transmutation. As can be seen from this table there are a large number of radionuclides, which cannot be transmuted due to complicating factors or because of the nature of the radionuclide. These include the medium-lived fission products, uranium (which forms about 95 percent of spent fuel), and many long-lived radionuclides that arise either from fission or from neutron activation.14 Of the long-lived fission products, only technetium-99 and iodine-129 have the potential to be fabricated into targets and transmuted in a reactor. The plutonium, and in some cases, the other minor actinides, would be made into fuel to run the transmutation reactor. The actinides could either undergo fission or capture a neutron, though for the purposes of transmutation, which is trying to reduce the amount of actinides, fission is preferred. Transmutation would also create significant quantities of additional transuranic and low-level waste, particularly if aqueous reprocessing is used. Furthermore, it has been proposed in the United States to dispose of uranium separated from spent fuel in a transmutation program as "low-level" waste in shallow land burial sites. This, along with the possible shallow-land disposal of other long-lived radionuclides, could result in an even greater overall radiological risk to the public from transmutation, compared to disposal of all spent fuel in an appropriately selected and engineered repository. The same observation is also likely to be true of worker and public health hazards arising from repeated reprocessing of spent fuel, fabrication of increasingly radioactive fuels and operation of new reactor types with which there is little commercial experience. Transmutation, even in the context of a phase-out of nuclear power, would also require decades to implement and possibly centuries to complete.15 This may require institutional control over the waste for time periods much longer than is feasible or desirable. Implications of Transmutation The implementation of any of the transmutation schemes discussed above would also have a number of implications for nuclear proliferation, the environment and human health, safety, cost, and the future of nuclear power. Proliferation. All transmutation schemes require reprocessing and separation of transuranic radionuclides. The current use of commercial reprocessing and MOX fuel, the simplest of schemes to transmute a small fraction of existing plutonium, results in the separation of significant quantities of plutonium, which is undesirable from a proliferation standpoint. The current mismatch between reprocessing capacity and reactor capacity for MOX use has meant that a significant stockpile of commercial separated plutonium has accumulated worldwide (including 30 metric tons in Russia). While some new transmutation schemes would materials that would be unattractive to weapons designers in nuclear weapons states, they are nonetheless weapons-usable and would pose significant proliferation risks. Non-state groups or non-weapons states that do not have weapons-usable materials today might seek to acquire and use them because they may be more available in less secure facilities. Even the reprocessing methods that are labeled as proliferation resistant, such as pyroprocessing, can be modified to allow for the extraction of plutonium pure enough to make weapons. Some reprocessing technologies proposed for transmutation may increase proliferation risks due to their compact size and attendant difficulty of detection. These would lead to new and more difficult problems in developing adequate safeguards in an already complex field. Furthermore, promotion of transmutation as a waste management tool may result in the widespread transfer of reprocessing technology. The separation of isotopes like neptunium-237 and americium-241 (which are two of the radionuclides produced during irradiation of fuel in a reactor) would also increase proliferation risks, since both of these radionuclides can also be used to make nuclear weapons. In sum, transmutation is a scheme that would greatly increase separation of weapons-usable material and/or the diffusion of technologies that would facilitate such separation. It will thereby considerably increase the risks of nuclear proliferation. Environment and Health. Reprocessing, which is required in all transmutation schemes, is one the most damaging components of the fuel cycle. It results in the discharge of large volumes of waste and radioactive emissions to air and water. Health and environmental concerns regarding reprocessing are the basis of the demands of Ireland, Norway, Iceland, and Denmark that Britain and France eliminate their so-called "low-level" radioactive waste discharges from their reprocessing plants into the seas. The increased radiological risk of handling fuel that has been repeatedly irradiated is cause for serious concern. Finally, the increased transportation of high level waste required under a number of transmutation schemes would increase the probability of a transportation accident. Reactor Safety. All transmutation schemes that would transmute significant amounts of plutonium and other transuranic materials require the use of reactors that are currently not commercial. Some schemes would use breeder reactors, which face serious technical issues even after five decades of development, and have not yet been commercialized. Other schemes would use accelerator-driven sub-critical reactors, which have not yet been built. Yet other schemes would use combinations of these two reactor types. Some new reactors, notably accelerator-driven sub-critical reactors, have been described as "inherently safe." However, increases in certain safety features, in comparison with commercial light water reactors, is countered by decreases in other safety features and the creation of new safety problems particular to the new reactor designs. According to Dr. Lawrence Lidsky of MIT's Nuclear Engineering Department, "sub-critical systems can actually be more dangerous than conventional reactors if, as is often the case, there are more subsystems that can fail or initiate failures, and fewer backups. Probabilistic risk analysis is a complex art, requiring a deep understanding of possible accident initiators and accident progression, and the ATW design is far too rudimentary at this time to apply this powerful tool. However, it is clear that the currently envisaged ATW systems are more complex than fission reactors, have more accident initiators, and many fewer backup safety systems." It is thus premature, at best, to label these reactors as inherently safe. And according to one eminent authority, they could be a lot more dangerous. There is therefore ample reason for caution. Cost. The cost of transmutation, particularly for the advanced schemes that would be required in order to have significant reduction of actinides, is prohibitively expensive (even in comparison to the billions to be spent on repository programs). Furthermore, while electricity would be produced to offset these costs, it is highly unlikely that these revenues will be sufficient. Transmutation would likely require tens of billions of dollars to develop, and additional large subsidies during operations, even after accounting for electric power sales. Even current uses of plutonium in reactors, both in light water reactors and in fast reactors, are not economical. The overall cost can be expected to be many tens of billions of dollars of net costs and overall investments up to hundreds of billions of dollars. Continuation of Nuclear Power. Transmutation is not only considered in the context of managing the waste from the current generation of nuclear reactors (i.e. as part of a phase-out of nuclear power). Most transmutation schemes, particularly in Europe and Japan, assume an indefinite continuation of nuclear power, with transmutation as one part of a new nuclear fuel cycle. By supposedly solving some of the current problems with nuclear power (particularly waste management, but also reactor safety in some cases), transmutation is seen by some as essential to ensuring the continued growth of nuclear power. Seen in this light, transmutation of waste is actually a Trojan horse for perpetuating nuclear power and hence the generation of more and more radioactive wastes for the indefinite future. This is surely not the way to solve the problem of managing radioactive waste from the current generation of commercial reactors. Conclusions and Recommendations Our main finding is that transmutation schemes will not solve long-term waste management problems. Well over 90 percent of the weight of spent fuel consists of uranium. According to according to current US proposals, the uranium would be treated as low-level radioactive waste and be disposed of in ways that will likely pose far greater risks than disposal in a carefully selected and engineered deep geologic repository. In addition, considerable quantities of transuranic materials would remain after transmutation, along with long-lived fission products. Large quantities of new waste would be created, along with new proliferation risks and high costs. Despite these severe limitations, transmutation continues to be seen by some as a "seductive" area of research and essential for revitalizing the "nuclear option." In light of these conclusions, IEER's main recommendation is that, because there is no sound technical basis for proceeding, transmutation should be abandoned as a waste management technology. Detailed findings and recommendations are given below.
Plutonium reprocessing operations pose unacceptable environmental, proliferation and financial risks and should cease. Existing stocks of separated plutonium should be immobilized (encasing it in a solid material like glass). This would reduce the proliferation risks of separated plutonium while not encouraging the further separation of plutonium from spent fuel. Feasibility studies should be conducted in the United Kingdom, France, and Japan (with the aid of the United States and Russia) on the conversion of MOX fuel fabrication facilities to ceramic immobilization facilities.19 High-level waste management has been plagued by short-sighted political expediency. For instance, in the United States only one site, Yucca Mountain, is being actively developed, which has resulted in severe pressures to open it despite extensive evidence of its unsuitability. Reforms should be implemented to stop politically expedient repository projects, and those, like transmutation, which seem to have keeping nuclear power alive as a subterranean goal. We need a broad-based scientific search for appropriate disposal options in contrast to efforts on transmutation. Much of the current technical literature on transmutation focuses on the possibility of transmutation to reduce the amount of actinides in high-level waste. This is a questionable approach, given the potential for significant increases in worker and public doses due to increased fuel cycle activities, inappropriate disposal of some reprocessing waste such as uranium, generation of more waste especially in reprocessing operations, and the open questions about the effect that transmutation will have on doses from a repository. All of these various risks need to be included in any overall analysis. At the very least transmutation programs should be suspended until such an analysis, conducted by an appropriate independent body, has been openly and thoroughly done with public input. In Europe and Japan, where transmutation research budgets are substantial, funds should be redirected to repository programs or other nuclear waste management programs that do not rely on reprocessing and nuclear reactors. Transmutation programs are diverting valuable resources from other, more appropriate, waste management options. Similarly, in the United States, further work on Accelerator Transmutation of Waste (ATW) or other transmutation schemes should be halted. Furthermore, the United States Department of Energy should halt all research on separation processes, including those based on electrometallurgical techniques. This research should be considered a violation of the federal policy against reprocessing of commercial fuel. We would like to thank Dr. Edwin Lyman, David Lochbaum, Greg Mello, Dr. Lawrence Lidsky, Hideyuki Ban, Dr. Yukio Yamaguchi, Monique Sené, and Jean-Pierre Morichaud for their review of one or more drafts of this report. Of course, the authors are solely responsible for the content of the report, its conclusions and recommendations, and any omissions or errors that remain. We would also like to thank IEER staff members Lois Chalmers, Diana Kohn, Betsy Thurlow-Shields, Michele Boyd and Arjun Makhijani for their comments and assistance. Research for this report was conducted as part of IEER's program: The Road to Enduring and Complete Nuclear Disarmament: A Technical Outreach Project on Nuclear Weapons and Related Energy Issues. We gratefully acknowledge the W. Alton Jones Foundation, John D. and Catherine T. MacArthur Foundation, the C.S. Fund, and the HKH Foundation for their generous support of this program. Outreach for this report will also be conducted as part of IEER's Project to Provide Technical Assistance to Grassroots Groups on Nuclear Issues, which is made possible by the support of the John Merck Fund, Ploughshares Fund, Public Welfare Foundation, Town Creek Foundation, and the Unitarian Universalist Veatch Program at Shelter Rock. We would also like to thank our individual donors and general support funding of the Beldon II Fund, Stewart R. Mott Charitable Trust, Rockefeller Financial Services, and Turner Foundation. (A complete list of references can be found in the full report.)
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1. There are over 400 nuclear power reactors currently operating worldwide. About 220,000 metric tons of spent fuel have been discharged from these reactors to date (the year 2000), and the number is increasing at a rate of about 10,000 metric tons per year. Almost 20 percent of the plutonium in this fuel has been extracted by reprocessing, while the rest is stored as spent fuel. See IAEA 1997b, p. 119, and Energy Information Administration, U.S. Department of Energy. World Spent Fuel Discharges, Reference Case, 1999-2020. http://www.eia.doe.gov/cneaf/nuclear/n_pwr_fc/data98/table10.html. For reprocessing data and estimates, see Albright, Berkhout, and Walker 1997, Chapter 6. 2. See Science for Democratic Action vol. 7, no. 3 (May 1999) for more information about issues related to the long-term management of nuclear waste, particularly in the United States, and for just some of the evidence concerning Yucca Mountain's unsuitability as a repository location. 3. Reactors do not necessarily have to produce electricity. For instance, with one exception, none of the reactors used to produce plutonium for nuclear weapons in the United States produced electricity. However, the sale of electricity is the only way to recoup some of the high costs associated with transmutation. This requirement can create its own problems, however, by raising the reliability requirements of some transmutation systems so as to not disrupt electricity supply once it is operational (see section on accelerator reliability in Chapter IV). 4. Accelerated protons hitting a target made of heavy metal, which produces neutrons through a nuclear reaction called spallation, would produce the supplemental neutrons. 5. Transmutation is also possible using photonuclear reactions, which use energetic photons to induce transmutation. Photonuclear transmutation schemes share many technical details with schemes discussed in this report and pose essentially the same major problems. However, phototransmutation is even less developed and would pose even greater research and development hurdles. 6. Reactions are shown in the footnotes with half-lives shown in parentheses. n = neutron; e = beta particle; m = metastable (an excited state of the nucleus that does not decay immediately to the ground state). Half-lives are rounded to two significant figures 7. I-129 (1.6x107 years) + n ® I-130m (9 minutes)® I-130 (12 hours) ® Xe-130 (stable) + e8. Cs-135 (2.3x106 years) + n ® Cs-136m (19 seconds) ® Cs-136 (13 days) ® Ba-136m (0.3 seconds) + e ® Ba-136 (stable)9. Cs-133 (stable) + n ® Cs-134 (2.1 years) + n ® Cs-135 (2.3x106 years)10. The reactions are: Pu-240 + n ® Pu-241 (14 years); Pu-241 (14 years) + n ® Pu-242 (380,000 years)11. ATW Roadmap 1999d. p. 38 12. In this case strontium-90 would also likely be disposed of in the repository, since its half-life is about the same as cesium-137. 13. For the first one hundred years the fission products dominate the radioactivity of spent fuel (with Cs-137 and Sr-90 being the predominant radionuclides). After 300 years it is the actinides which dominate the radioactivity. Both fission products and actinides contribute to the radioactivity in the period between 100 and 300 years (see NAS-NRC 1983, p. 30). 14. Neutron activation refers to a process by which materials that are not originally radioactive become radioactive after being irradiated with neutrons (e.g. structural materials in the core of a reactor or the material that surrounds the reactor fuel). 15. NAS-NRC 1996, p. 5 and OECD-NEA 1999b, p. 204. Some transmutation schemes would store medium-lived fission products for up to 600 years in order to allow them to decay (see Rubbia et al. 1997). 16. Though not addressed extensively in this report, it must be noted that each of the new facilities operated for the purposes of transmutation will eventually have to undergo decontamination and decommissioning procedures. This will result in even greater amounts of radioactive waste for disposal, including major components of the facilities such as the reactor cores. It is not clear how the increased radioactivity of fuel which has been repeatedly irradiated will affect the D&D process and the disposal requirements. 17. ATW Roadmap cost estimate (ATW Roadmap 1999g) adjusted to reflect more realistic reprocessing costs as established by the National Research Council (NAS-NRC 1996). Figures are in undiscounted 1999 dollars. 18. See Chapter V 19. The issue of separated commercial plutonium will be further explored in a forthcoming report by IEER. |
Institute for Energy and Environmental Research
May 2000
Full report web posted May 2005