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Phase II Final Report of Feasibility Study
on Commercialized Fast Reactor Cycle Systems
Executive Summary
March, 2006
Japan Atomic Energy Agency
The Japan Atomic Power Company
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The “Feasibility Study on Commercialized Fast Reactor (FR) Cycle Systems” (hereinafter, “Feasibility Study”) was initiated in July, 1999 with an initial two-year period of study (Phase I), and followed by a five-year period of study (Phase II) that was initiated in 2001. The Phase II final report was recently compiled, and the outline of the Phase II study is as follows: 1. Progress of the Feasibility Study Taking into consideration the recommendations on Dec., 1997 by the “Round-Table Conference on Fast Breeder Reactor (FBR)” of the Atomic Energy Commission of Japan and other discussion results, the Japan Atomic Energy Agency (JAEA) and electric utilities initiated the Feasibility Study in July, 1999 in collaboration with the Central Research Institute of Electric Power Industry (CRIEPI) and manufacturers, in order to effectively utilize the accumulated knowledge from the demonstration fast breeder reactor (DFBR) design, as well as the construction/operation experience from an experimental FR, JOYO and a prototype FBR, MONJU. The objective of this study is “to present both an appropriate picture of commercialization of the FR cycle and the research and development (R&D) programs leading up to the commercialization in approximately 2015.” A wide range of technical options have been evaluated to select several promising concepts as candidates for the commercialization in the Phase I study from July 1999 to the Japanese fiscal year (JFY) 2000. The Phase II study was initiated in JFY2001, aiming “to identify the most promising candidate concept for the commercialization of the FR cycle, as well as to draw up the future R&D program”. Based on recent progress, it was required by the “Framework for Nuclear Energy Policy” issued in 2005 to present “a principle for prioritizing R&D as well as R&D programs until approximately 2015, and the potential future issues” as the outcomes of the Phase II study. In this study, evaluation of conceptual design features was performed in order to select promising FR systems and fuel cycle systems that can meet the design requirements (listed in Table 1), established by specifying the five development goals [ i) safety; ii) economic competitiveness; iii) reduction of environmental burden; iv) efficient utilization of nuclear fuel resources; and v) enhancement of nuclear non-proliferation]. 2. Principle for investigation and prioritization of promising candidate concepts In creating the concepts of the FR system and the fuel cycle system, efforts were made to set up design concepts that can demonstrate the best possible performance of each of the system concepts, by positively employing new materials and innovative technologies to improve economic and other performance. These design concepts were evaluated technically from two perspectives, [ i) potential conformity to the five development goals, ii) the pro tem technical feasibility of new materials and innovative technologies by considering possible international cooperation], to discuss principles for the selection and prioritization of promising candidate concepts. In addition, some of the adopted new materials and innovative technologies have a high level of technical difficulty; however, it was assumed that even such materials and technologies should be applicable, as expected in this study. Therefore, it is necessary to form a clearer view of the feasibility by conducting elemental experiments and research on each of the materials and technologies. 2.1 Technical summary of FR systems 2.1.1 Sodium-cooled reactor (Figure 1)
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To improve economy, new materials, including ODS (Oxide Dispersion Strengthened) steel cladding and high-chromium steel, as well as innovative technologies such as the compact reactor vessel, the integrated intermediate heat exchanger with primary pump and a reduction in the number of heat transport loops (two loops for a 1.5GWe plant) were adopted. In addition, an increase in the capacity of each component was employed to establish drastically-compacted plant system concepts compared with the conventional concepts, and, thereby, greatly reduce the amount of plant materials and its building volume. Reduction in the fuel costs by increasing the core fuel burnup (150GWd/t; core-averaged value) and in the operating costs by extending the operation period (18-26 months) resulted in the possibility of achieving the goals of power generating costs. A high level of potential conformity to design requirements including the reduction of environmental burden and the efficient utilization of nuclear fuel resources was confirmed in the case of mixed oxide (MOX) fuel. Furthermore, additional improvements were made from the perspective of enhancing safety and reliability by the addition of a passive shutdown function, the assurance of core cooling function by natural circulation, the application of double-walled heat transfer tube for the steam generator, and the complete adoption of a double-walled piping geometry. On the other hand, as sodium is opaque and chemically active, it is necessary to pay great attention to both maintainability and repairability from the design stage to assure plant reliability. For this reason, maintenance and repair guidelines that would be needed for a commercial FR were discussed by considering the advantages of sodium including good compatibility with structural materials, with reference to efforts and trends of maintainability and repairability for light water reactors (LWRs). Design studies were performed so as to conform to the maintenance and repair guidelines, and development of required inspection equipment was initiated. It is still necessary to continue the development of inspection and repair technologies; however, when considering the experiences of developing inspection devices at MONJU and the DFBR study as well as the testing results of inspection equipment obtained in the Phase II study, in addition to the actual results of operation and maintenance at JOYO, it is considered possible to assure maintainability and repairability equivalent to those of LWRs in the future. Issues seriously affecting technical feasibility are mainly limited to the technical development required to achieve the economic goal. However, innovative technologies having a high level of technical difficulty could be replaced by alternative technologies, which are extensions of existing technologies and achieved with less significant development risk, though with a degradation in economy. Accordingly, when considering the development performance including that of MONJU and DFBR, it is possible to anticipate technical feasibility with a higher degree of reliability than other concepts. In addition, the sodium-cooled reactor was selected as one of the candidate reactor types in the Generation IV International Forum (GIF) project that is actively promoted in multilateral cooperation, and the sodium-cooled reactor design concept in this Phase II study has become a representative candidate concept of such a reactor type within the GIF project. Therefore, it is possible that the sodium-cooled reactor design concept in this study may be developed as an international standard, and, furthermore, it is expected that technical feasibility can be enhanced by an international sharing of the
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research tasks to be addressed for the realization. Moreover, applying metallic fuel for sodium-cooled reactors makes possible the design of a core with a higher breeding ratio with less Pu inventory, in addition to an improvement of the economy through increased average fuel burnup including blanket fuel. For example, maintaining the equivalent fuel burnup of the future LWR(55GWd/t), a metallic fuelled core can assure a breeding ratio of ~1.26 compared with ~1.20 of a MOX fuelled core, as well as less fuel inventory than the MOX core by 11%. From these results, it is expected that the sodium-cooled reactor can cope flexibly with the possible tight supply-demand situation for uranium resources in the future which might be caused by a more accelerated introduction of FR or an increased nuclear power generation capacity than is presently anticipated. 2.1.2 Helium gas-cooled reactor The helium gas-cooled reactor has the potential of meeting all the design requirements through the application of nitride fuel; however, its fuel cycle cost is increased due to the lower fuel burnup than that of the sodium-cooled reactor. On the other hand, since it allows a high reactor outlet temperature of approximately 850℃, it is attractive as a high temperature heat source that can not be realized with the sodium-cooled reactor. Concerning the technical feasibility, the development of coated particle nitride fuel should be an essential technical consideration that will determine the conceptual applicability. Specific issues include the development of coating material for particle fuel as well as a block-typed fuel subassembly that has high temperature resistance, which would require fundamental R&D and are not likely to be replaced by alternative technology at this stage. On the other hand, since the helium gas-cooled reactor was selected as one of the candidate reactor types at the GIF project, it may be possible to break through these fundamental issues in international cooperation. 2.1.3 Lead-bismuth-cooled reactor By applying nitride fuel, the lead-bismuth-cooled reactor has the potential to achieve core performance equivalent to the sodium-cooled reactor and meet all the design requirements. Concerning technical feasibility, essential issues include the corrosion of steel such as the fuel cladding in addition to the development of the nitride fuel. Accordingly, fundamental R&D is needed to develop corrosion prevention technology and corrosion resistant material, which will determine the conceptual applicability. It is quite difficult to prepare alternative technologies for these issues at this stage. Although the lead-bismuth-cooled reactor was also selected as one of the candidate reactor types at the GIF project, no country has taken leadership in its development thus far, and, hence, a breakthrough in the fundamental issues by international cooperation is unlikely. 2.1.4 Water-cooled reactor As for the efficient utilization of nuclear fuel resources in the design requirements, the lower breeding ratio and larger fuel inventory of the water-cooled reactor require more time for the transition into the FR era and consequently reduce the introduction effect as FR from the viewpoint of saving natural uranium resources. In addition, the water-cooled reactor has lower performance in accepting and burning minor actinides (MAs) that are recovered by the reprocessing of spent LWR fuel, compared with other reactor concepts. It has the potential of meeting the other design requirements such as safety, economy, and nuclear proliferation resistance.
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In order to anticipate the technical feasibility, the water-cooled reactor has difficulties, which are, however, limited to the core fuel related issues. It is necessary to develop cladding material and to discuss countermeasures for the mitigation of the consequences of core damage. In addition, since boiling water reactor (BWR)-typed FR, which was discussed in this study, was not selected as a candidate reactor type at the GIF project, international cooperation is limited to basic research topics at this time. 2.1.5 Promising concepts for the FR system Promising concepts for the FR system have been identified based on the technical summary results of candidate concepts for the FR system as shown in Table 2. The sodium-cooled reactor is superior to other reactor types from the perspective of both potential conformity to the design requirements and technical feasibility. Furthermore, since it has the potential to be adopted as an international standard concept, which may help to enhance technical feasibility, it is evaluated as the most promising FR system concept. The helium gas-cooled reactor has the potential to meet all the design requirements, and also has the potential to accommodate the various needs as a high temperature heat source, which makes the helium gas-cooled reactor different from all other reactor types. Although it has fundamental problems that will determine conceptual applicability, several countries, including the USA and France, have shown eagerness for its development, and there is a good possibility of solving difficulties through international cooperation. The other FR concepts cannot become superior to the above-mentioned promising ones from the perspective of either the potential conformity to design requirements or technical feasibility. 2.2 Technical summary of fuel cycle systems 2.2.1 Combination of the advanced aqueous reprocessing system and the simplified pelletizing fuel fabrication system (Figure 2) The advanced aqueous system can eliminate “the purification process of U product and Pu product,” which is one of the main processes in the conventional technology (PUREX process), because a certain amount of fission products (FPs) in recycled fuel (low decontamination) can be accepted into the FR cycle. In addition, the introduction of crystallization technology, which will recover approximately 70% of the uranium dominating (approximately 80%) the heavy metal (HM) mass in the solution of spent fuel beforehand, allows a drastic reduction in the throughput in the following processes, leading to a streamlining of installations. The powder mixing process dominating a large part of the conventional pelletizing process can be eliminated by making it possible to control Pu content through the mixture of U and Pu in the nitric acid solution stage. An integrated layout of a reprocessing system and a fuel fabrication system also results in a rational facility design. On the other hand, when compared with the conventional concepts, this concept has cost increase factors, including the addition of the MA recovery process in the reprocessing system as well as the necessity of a hot cell in the fuel fabrication system where the low decontaminated fuel can be handled. As described above, this concept has both advantageous and disadvantageous impacts on economy; however, the advanced aqueous reprocessing system can greatly affect
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streamlining, such as almost halving the construction costs compared with the conventional technology through process elimination and the streamlining of installations that are realized by the lowered decontamination. Accordingly, there is a possibility of meeting the design requirement on economy. The possibility of meeting the design requirements, including efficient utilization of nuclear fuel resources, reduction of environmental burden and enhancement of nuclear non-proliferation is evident as well. The advanced aqueous reprocessing system requires the development of processes and components for new technologies such as the crystallization and the MA recovery; however, since abundant technical knowledge obtained through experiences at the Tokai Reprocessing Plant in JAEA and at the Rokkasho reprocessing plant in the Japan Nuclear Fuel Limited can be utilized, it is possible to anticipate the technical feasibility with a high degree of reliability. Furthermore, as the advanced aqueous reprocessing system is the focus of development in France, enhancement of the technical feasibility is expected through international cooperation. It becomes necessary to develop components with consideration given to remote maintainability and repairability to address the fuel fabrication in a hot cell; however, as basic processes of the simplified pelletizing fuel fabrication system are common to those of the conventional processes, it is possible to anticipate the feasibility with a high degree of reliability. Besides, the fundamental research of the supercritical direct extraction process, which can simultaneously perform both the dissolution of spent fuel and the extraction of U and Pu, continues, because it has the potential to further simplify the system configuration, and to allow better streamlining in aspects of economy and the amount of waste generation of the advanced aqueous reprocessing. 2.2.2 Combination of the metal electrorefining reprocessing system and the injection casting fuel fabrication system Fuel reprocessing by the metal electrorefining recovers U and TRU from spent metallic fuel using the principle of the electrolytic refining, and fuel fabrication by the injection casting process casts fuel by melting the recovered U and TRU, and both systems allow more simplified processes compared with the other fuel cycle systems. It has been confirmed through the results of previous investigations that the combination system creates the potential of meeting all the design requirements. Especially in the case of a small-scale cycle facility, it is anticipated to have better potential conformity to the economy requirement than the other systems. However, it is anticipated that the economy of a large-scale facility will be inferior to that of the “combination of the advanced aqueous reprocessing system and the simplified pelletizing fuel fabrication system” because the batch process mode of both the reprocessing and fuel fabrication systems can not obtain a good scale factor. Moreover, the volume of high-level radioactive solidified waste (HLW) per unit electricity output becomes larger than the other fuel cycle system concepts because of the limited amount of FPs that can be mixed in HLW, which is generated through the metal electrorefining reprocessing and processed into glass-bonded sodalite (the raw material is zeolite). Since it is considered that the applicability of the main processes has almost been confirmed when considering the development performance in the USA, it is possible to anticipate technical feasibility.
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The remaining considerations include confirmation of process applicability by using spent fuel, the reduction in the amount of HLW, and the development of components with consideration given to remote maintainability and repairability. Although the technical difficulties of those considerations are not high, development is anticipated to take a considerable amount of time because domestic infrastructure for the development is insufficient. For this reason, international cooperation with the USA, a country that has development performance, and other countries, should be important. 2.2.3 Combination of the advanced aqueous reprocessing system and the vibration packing fuel fabrication system When the vibration packing fuel fabrication system is coupled with the advanced aqueous reprocessing system, spherical fuel particles are manufactured by the “gelation process”, which produces good results in the manufacture of fuel of the high-temperature gas-cooled reactor (HTTR, etc.), and packed in cladding. Accordingly, it can eliminate the powder mixing process which dominates a large part of the conventional pelletizing fuel fabrication system. Furthermore, it has additional advantages such as fine powder not being generated and better suitability for remote maintainability and repairability compared with the simplified pelletizing fuel fabrication system. Achieving superior economy was once expected through the utilization of these advantages; however, inferior economy to the simplified pelletizing fuel fabrication system has been anticipated because it becomes essential to be equipped with large and small particle manufacturing lines in order to realize the packing density of fuel. Although the vibration packing fuel fabrication system has the potential of meeting all the design requirements, a system superior to the simplified pelletizing fuel fabrication system is unlikely. Concerns include the development of components with consideration given to remote maintainability and repairability, and the inspection technique for axial distribution of the packing density of fuel. Less technical knowledge has been obtained compared with the simplified pelletizing fuel fabrication system; however, since the applicability of the system was confirmed by the manufacture performance of MA-bearing fuel, feasibility can be anticipated. Concerning the “nitride coated particle fuel” that is compatible with the helium gas-cooled reactor, the addition of appropriate processes, including decladding, nitriding and coating, makes it possible to apply the advanced aqueous reprocessing as well as the “gelation process”(a part of the vibration packing fuel fabrication system) for manufacturing fuel. In this manner, a fuel cycle system suitable for the nitride coated particle fuel has a number of technical features in common with the “combination of the advanced aqueous reprocessing system and the vibration packing fuel fabrication system”, and, consequently, it is efficient to initiate the technology development on the basis of progress in FR system development such as the development of the nitride fuel subassembly. Problems concerning the nitride coated particle fuel include decladding technology in reprocessing and coating technology in manufacturing fuel, as well as the development of the above-mentioned coating material and the fuel subassembly. In addition, for the nitride fuel, it is necessary to enrich (targeting on 99.9%) and apply 15N, which has less natural abundance (0.37%), in order to suppress the generation of 14C, which has a long half-life, in the fuel. For this reason, it will become necessary to develop a less expensive 15N enrichment technology, as well as a 15N recycling technology.
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2.2.4 Combination of the oxide electrowinning reprocessing system and the vibration packing fuel fabrication system Fuel reprocessing by the oxide electrowinnig recovers UO2 and MOX from spent MOX fuel using the principle of electrolysis, and fuel fabrication by the vibration packing process packs fuel granules, that are obtained by crashing the fuel recovered on the cathodes, in the cladding, and the combination of the two allows a simple system, as well as cases applying the metal electrorefining system. Investigations show the potential of its meeting all the design requirements including economy. However, the MOX and MA recovery technologies are still undergoing a verification of principles, and there remain a number of technical issues, such as countermeasures against material corrosion arising from the application of chlorine gas and oxygen gas, development of remote maintainability and repairability, and quality control of the fuel granules. Therefore, technical feasibility is inferior to the other concepts. Moreover, since it would require a domestic development infrastructure, development is anticipated to take a considerable amount of time. 2.2.5 Promising concepts for the fuel cycle system Promising concepts for the fuel cycle system have been identified based on the technical summary results of candidate concepts for the fuel cycle system (Table 3). “Combination of the advanced aqueous reprocessing system and the simplified pelletizing fuel fabrication system,” which can cope with either MOX or nitride fuel, has potential conformity to the design requirements, as well as a high level of technical feasibility because it can be developed with an extension of the existing technologies. In addition, since it is expected to be developed through international cooperation, it is evaluated as the most promising fuel cycle system concept. “Combination of the metal electrorefining reprocessing system and the injection casting fuel fabrication system” applied to metallic fuel that can improve core performance has the potential of meeting design requirements and is likely to have better small-scale cycle facility economy than the other concepts, in particular. Concerning technical feasibility, long-term development may be required; however, since international cooperation with the USA and other countries can be expected, it is suggested to be a promising fuel cycle concept. The other fuel cycle concepts cannot achieve superiority over the above-mentioned promising concepts from the perspective of either potential conformity to the design requirements or technical feasibility. 2.3 Discussion on the principle for prioritization 2.3.1 Evaluation of the entire FR cycle system In selecting promising FR cycle concepts, it is appropriate to evaluate potential conformity to the development goals, technical feasibility and other factors of not only the FR system and the fuel cycle system, respectively, but also the entire FR cycle system that is the combination of the two systems. In the above-mentioned technical summary, it is concluded, for the FR system, that the “sodium-cooled reactor” is the most promising concept and the “helium gas-cooled reactor” is a promising concept. On the other hand, it is concluded, for the fuel cycle system, that the “combination of the advanced aqueous reprocessing system and the simplified pelletizing fuel fabrication system” is the most promising concept and the
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“combination of the metal electrorefining reprocessing system and the injection casting fuel fabrication system” is a promising concept. In the evaluation of the FR cycle, promising FR cycle concepts have been established based on the technical summary results on respective FR and fuel cycle systems. The established concepts are described in the following: (1) “Combination system of the sodium-cooled reactor, advanced aqueous reprocessing and simplified pelletizing fuel fabrication” (MOX fuel) As this concept has the greatest potential conformity to the development goals, including economy (power generating costs), and as it is possible to anticipate its technical feasibility, it can be judged the most superior concept. (2) “Combination system of the sodium-cooled reactor, metal electrorefining reprocessing and injection casting fuel fabrication” (metallic fuel) This concept is not considered to be superior to the concept (a) in the comprehensive evaluation concerning the potential conformity to the development goals and technical feasibility; however, since it can improve the core performance by employing metallic fuel, it can be judged as being more attractive in terms of flexibly coping with possible future situations, such as tighter supply-demand for uranium resources than presently expected. (3) “Combination system of the helium gas-cooled reactor, advanced aqueous reprocessing and coated particle fuel fabrication” (nitride fuel) This concept is not considered to be superior to the concept (a) in the comprehensive evaluation concerning the potential conformity to the development goals and technical feasibility; however, since it can realize high reactor outlet temperature, it can be judged as being more attractive than (a) in terms of accommodating the various needs as a high temperature heat source. 2.3.2 Principle for prioritization In order to prioritize R&D, the above-mentioned concept (a) is selected as “the concept to be developed with a focus on (principal concept)” because it is judged to be the most comprehensively superior concept by the technical summary. In addition, it is decided to designate those concepts having more attractiveness than the principal concept as “concepts to be developed in a complementary manner (complementary concept)” from the perspective of assuring diverse alternatives to uncertainties, including future needs, and the above-mentioned concepts (b) and (c) are selected as the complementary concepts. In the future, the main R&D investment should be focused on the principal concept in consideration of efficient utilization of the limited research resources. In parallel, concerning the complementary concepts, R&D should be conducted with a focus on concerns that are judged as essential for technical feasibility and other aspects. 3. R&D Strategy in Phase III and beyond 3.1 R&D Prospects until approximately 2015 (Figure 3) In the Phase II study, selection of promising candidate concepts for commercialization, establishment of the principle for prioritizing R&D concerns and development of the
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R&D program until approximately 2015 have been conducted. In parallel, concerning the prioritized concepts, perspectives on fundamental applicability have been obtained by elemental experiments and research on each of innovative technologies. In the Phase III study and beyond, by approximately 2015, technical schemes will be developed, including preparation of data that will determine the applicability of commercial plants based on elemental test results and the presentation of technical specifications of commercial plants, with the aim of the “presentation of the commercialization picture and the R&D program required for realization”. Throughout the duration of the timeframe, R&D will be conducted efficiently with repeated check & review at each interim summary (every 2-3 years) as well as at the end of each Phase. Further, the strategy for developing the principle and complementary concepts will be reviewed in each Phase by taking into account various situations, including trends in international development as well as the energy supply and demand conditions. In the Phase III study, elemental experiments and research will be conducted in order to evaluate the applicability of innovative technologies, and a conceptual design study of a total system of innovative plants will be conducted. Based on results of these, it will be decided which innovative technologies should be adopted; and it may become necessary to substitute more applicable technologies (e.g., alternative technologies) for any innovative technologies presenting applicability concerns. In the Phase IV study, elemental experiments and research on the applicability of the adopted innovative technologies as well as an optimization study of the innovative plant to be conceptually-designed in the Phase III study will be conducted to present the commercialization picture and R&D program for realization. 3.2 R&D program for FR systems 3.2.1 Sodium-cooled reactor At the end of the Phase III study (~2010), innovative technologies to be adopted in the FR system will be decided by judging the applicability of new materials, including the ODS steel cladding and high-chromium steel, as well as of innovative components, such as an integrated intermediate heat exchanger with primary pump, a compact reactor vessel and a steam generator with double-walled heat transfer tube, and also from inspection technology prospects for components under sodium and double-walled heat transfer tubes as well as maintenance technologies, including in-service inspection (ISI) and maintenance standards, to establish a concept of a commercial reactor that excels in economy, maintainability and repairability, and other features. Concerning oxide fuel, the irradiation of fuel pins and TRU fuel pins using the ODS cladding will be continued to reach 40-60% of the targeted fluence (250GWd/t: pin peak value) so as to confirm integrity in the initial irradiation period. While, considering metallic fuel, irradiation of TRU fuel pins under high temperature condition (650℃) will be conducted to confirm integrity in the initial irradiation period. In the Phase IV study, based on the commercial reactor concept to be established in the Phase III study, elemental experiments on the adopted innovative technologies (including maintenance and repair technologies) will be conducted to confirm applicability, and the conceptual design will be optimized by reflecting those confirmation results.
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Concerning oxide fuel, irradiation of fuel pins and TRU fuel pins using the ODS cladding will be continued to confirm integrity at the targeted fluence, and, in parallel, irradiation data will be developed for experimental data required for the commercialization. While, considering metallic fuel, irradiation integrity will be confirmed up to a high burnup, and the validity of measures to avoid recriticality will be verified by experimental research. In the sodium-cooled reactor R&D of the GIF project, the estimated completion of the conceptual design is approximately 2010, to select a sodium-cooled reactor concept which should be subsequently developed. Aiming for this selection, efforts will be devoted to steady progress in design study as well as in elemental experiments and research, and to further cooperation with the GIF project, so as to allow the sodium-cooled reactor concept discussed in this study to be developed as an international standard. 3.2.2 Gas-cooled reactor As the gas-cooled reactor is a complementary concept, investigation will be focused on the nitride coated particle fuel, key to the conceptual applicability. For this purpose, in the Phase III study, investigation of innovative concepts of core and fuel consisting of ceramic material will be performed by utilizing information exchange through international cooperation such as the GIF project followed by a discussion of R&D strategy based on the results. In addition, the strategy of the Phase IV study and beyond will be decided at the end of Phase III. 3.3 R&D program for fuel cycle systems 3.3.1 Combination of the advanced aqueous reprocessing system and the simplified pelletizing fuel fabrication system In the Phase III study, innovative technologies to be adopted will be decided by judging the applicability of the crystallization process, the MA recovery, and other technologies based on small-scale hot test results. In addition, commercial component concepts will be presented in consideration of remote maintainability and repairability in the main processes. Based on these elemental experiment and research results, the commercial fuel cycle concept will be established. In parallel, the applicability of the supercritical direct extraction process, an alternative technology for the advanced aqueous reprocessing, will be carefully studied, and a judgment will be made as to whether or not it will be adopted. In the Phase IV study, elemental experiments and research, including process tests and component development relating to innovative technologies, will be performed to develop data that will determine the technical feasibility (including remote maintainability and repairability). Using these results, an optimization study will be carried out on the conceptual design of the commercial fuel cycle facility so as to present the technical specification by the development of technical schemes (by approximately 2015). Furthermore, the concept and test program of a test facility for technology demonstration will be concretely specified, and an R&D program to achieve commercialization will be presented. 3.3.2 Combination of the metal electrorefining reprocessing system and the injection casting fuel fabrication system As the “combination of the metal electrorefining reprocessing system and the injection casting fuel fabrication system” is a complementary concept, R&D will be conducted on
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an appropriate scale, with efforts to build a cooperative relationship with the USA and others. In the Phase III study, establishment of component concepts of the main processes, planning of small-scale hot tests and establishment of the commercial fuel cycle facility concept will be carried out. In addition, R&D will be conducted with a higher priority given to those problems which have less potential conformity to design requirements, including the reduction in the amount of HLW. In the Phase IV study, it is planned that development of the main process components and preparation for small-scale hot tests will be addressed to confirm conformity to the development goals and a subsequent comparative evaluation will be performed with the principle concept at the end of the Phase IV. However, concerning the R&D strategy in the Phase IV study and beyond, review should be made by the end of the Phase III, by taking into account situations both domestically and internationally, including the establishment of cooperative relationships with the USA and other countries. 3.4 Discussion on transition into the FR cycle In order to facilitate the smooth transition from LWRs to FRs in approximately the year 2050 and beyond, when the introduction of FRs on a commercial basis is anticipated, a long-term mass flow analysis concerning the mass balance of U, Pu, etc., has been performed to calculate the required reprocessing amount and the spent fuel stockpile from the perspective of fuel supply. In addition, in order to discuss a strategy for the achievement of the transition in a reasonable manner, the applicability of FR reprocessing technology to LWR reprocessing was discussed to identify future concerns. The mass flow analysis was performed by assuming the fixed nuclear power capacity (58GWe) beyond 2030 and the initial deployment of a FR fleet in 2050, to obtain such conclusions as that the transition from LWRs to FRs can be achieved in approximately 60 years, and that the achievement of the transition will require the reprocessing of not only FR fuel but also LWR fuel in order to supply Pu (TRU fuel) for FRs. In such a LWR fuel reprocessing, it will be effective to employ reprocessing technology for FR fuel (the advanced aqueous reprocessing system) that can streamline the LWR reprocessing system. As it is possible to cope with the LWR fuel reprocessing by employing the reprocessing technologies for FR fuel, it is not necessary for the moment to reexamine the R&D program described in 3.(3). However, since a discussion on a new reprocessing plant to follow the Rokkasho reprocessing plant is planned to begin in approximately 2010, it is considered effective to investigate the applicability of FR reprocessing technologies to LWR fuel reprocessing more specifically by that time. 4. Issues concerning the strategy beyond approximately 2015 In order to obtain a clearer view of whether or not the development of the technical schemes as planned by approximately 2015 would definitely lead to the introduction of a FR fleet in approximately 2050, a case study was conducted on R&D strategies beyond approximately 2015. In parallel, issues concerning R&D beyond approximately 2015 were identified. 4.1 Staged R&D of the FR cycle beyond approximately 2015 (Figure 4) As it is extremely risky and difficult to immediately aim at the construction and operation of middle or large-scale commercial plants employing numbers of innovative technologies toward the introduction of a FR cycle fleet on a commercial basis, it is
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necessary to step by step increase the scale of facilities and components, and to verify conformity to the development goals as well as the feasibility and reliability of the innovative technologies. For this purpose, it is considered desirable that the entire development process be divided into three stages, i.e.: the 1st stage, to develop the technical schemes of the FR cycle until approximately 2015; the 2nd stage, to have a clear view of the commercialization by demonstrating the FR cycle technologies using a test facility for technology demonstration; and the 3rd stage, to confirm economy and the reliability as well as to accumulate operating experience by using a commercialization promotion facility aiming at the introduction of a FR fleet on a commercial basis. 4.2 Issues beyond approximately 2015 As the Government plans to begin discussions in approximately 2015 on a staged R&D program leading to FR introduction on a commercial basis in approximately 2050, discussions are required to give more concrete form to the following subjects. In particular, on the strategy in the second stage, discussions are required to be advanced by the next revision of the Framework for Nuclear Energy Policy, in which discussion of the strategy is anticipated. i) How R&D (FR system, fuel cycle system) should be carried out in each stage Contents, execution period, scale, required funds, and international sharing of R&D tasks in the 2nd stage (demonstration of innovative technologies) and the 3rd stage (promotion of commercialization). ii) Sharing of roles for the development and retention of technologies after the demonstration stage Development of an organization that considers the sharing of roles between public and private sectors (Ministry of Education, Culture, Sports, Science and Technology; Ministry of Economy, Trade and Industry; private sectors) and the retention of technologies in the 2nd and the 3rd stages.
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im to
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ease
bu
rnup
of th
e w
hole
cor
e an
d pr
olon
g co
ntin
uous
ope
ratio
n pe
riod,
for i
mpr
ovin
g ec
onom
y du
ring
the
trans
ition
per
iod
from
LW
Rs
to F
Rs
•In
add
ition
to u
tiliz
atio
n as
a b
asic
pow
er s
ourc
e, m
ulti-
purp
ose
use
and
high
ther
mal
effi
cien
cy is
pos
sibl
e (D
esire
d)
Effic
ient
ut
iliza
tion
of
nucl
ear f
uel
reso
urce
s
•R
adio
activ
e w
aste
vol
ume
gene
rate
d pe
r uni
t ele
ctric
ity o
utpu
t is
requ
ired
to b
e eq
uiva
lent
to o
r les
s th
an th
at o
f the
LW
R fu
el
cycl
e fa
cilit
y, a
nd ta
rget
ed to
redu
ce to
1/1
0.•
Leak
age
ratio
of U
and
TR
U in
to w
aste
equ
al to
or l
ess
than
0.
1% (D
esire
d)•
Purs
ue th
e po
ssib
ility
of r
educ
ing
the
disp
ositi
on b
urde
n by
ad
optin
g pa
rtitio
n an
d tra
nsm
utat
ion
tech
nolo
gy o
f lon
g-liv
ed
radi
oact
ive
nucl
ides
, etc
.
•Can
acc
ept l
ow d
econ
tam
inat
ed T
RU
fuel
(with
~5%
of M
A co
nten
t) in
ord
er to
allo
w e
cono
mic
al b
urni
ng o
f MA
to b
e re
cove
red
from
LW
R s
pent
fuel
•Nuc
lear
tran
smut
atio
n pe
rform
ance
of l
ong-
lived
FPs
Red
uctio
n of
en
viro
nmen
tal
burd
en
•R
epro
cess
ing
and
fuel
fabr
icat
ion
cost
: ¥0.
8/kW
h•
Fuel
cyc
le c
ost i
nclu
ding
tran
spor
tatio
n an
d w
aste
dis
posa
l fee
:¥1
.1/k
Wh
•C
onst
ruct
ion
cost
: ¥2
00,0
00/k
We
•Fu
el c
ost:
Cor
e-av
erag
ed fu
el b
urnu
p: 1
50G
Wd/
t•
Ope
ratin
g co
st:
-Con
tinuo
us o
pera
tion
perio
d eq
ual t
o or
long
er th
an 1
8 m
onth
s-A
vaila
bilit
y eq
ual t
o or
long
er th
an 9
0%
Econ
omic
co
mpe
titiv
enes
s¥4
/kW
h fo
r pow
er
gene
ratin
g co
st a
s a
FR c
ycle
sys
tem
•Eq
uiva
lent
or s
uper
ior t
o th
e LW
R fu
el c
ycle
sys
tem
of t
he s
ame
age
(elim
inat
ing
occu
rren
ce fa
ctor
s of
abn
orm
aliti
es to
the
utm
ost,
prev
entin
g pr
opag
atio
n of
abn
orm
aliti
es, e
tc.)
•R
ealiz
e a
desi
gn th
at c
an s
uppr
ess
the
occu
rrenc
e fre
quen
cy o
f la
rge
rele
ase
even
ts o
f rad
ioac
tive
mat
eria
l in
a fa
cilit
y to
less
th
an 1
0-6
per p
lant
yea
r, an
d as
sure
con
finem
ent f
unct
ion
of th
e fa
cilit
y ev
en w
hen
assu
min
g su
ch a
n ev
ent,
to p
rodu
ce a
n in
sign
ifica
nt in
fluen
ce o
n th
e su
rrou
ndin
g en
viro
nmen
t
•O
ccur
renc
e fre
quen
cy o
f cor
e da
mag
e is
less
than
10-
6pe
r re
acto
r yea
r.•
Enha
ncem
ent o
f pas
sive
saf
ety
mea
sure
s ag
ains
t re
pres
enta
tive
even
ts p
ossi
bly
lead
ing
to c
ore
dam
age,
or
conc
retiz
atio
n of
acc
iden
t man
agem
ent m
easu
res
•C
an a
void
the
occu
rrenc
e of
recr
itica
lity
durin
g hy
poth
etic
al
core
dam
age
and
ensu
re th
e ce
ssat
ion
of e
ffect
s in
side
reac
tor
vess
el o
r con
tain
men
t fac
ility
Safe
ty
Des
ign
requ
irem
ents
for f
uel c
ycle
sys
tem
Des
ign
requ
irem
ents
for F
R s
yste
mD
evel
opm
ent g
oal
Tabl
e 1
Dev
elop
men
t goa
ls a
nd d
esig
n re
quire
men
ts
- 14 -
Diff
icul
t to
antic
ipat
e in
tern
atio
nal c
oope
ratio
n.
As
it is
not
sel
ecte
d as
a
cand
idat
e co
ncep
t at G
IF,
inte
rnat
iona
l coo
pera
tion
is li
mite
d to
bas
ic
rese
arch
topi
cs a
t thi
s tim
e.
Diff
icul
t to
antic
ipat
e in
tern
atio
nal
coop
erat
ion.
No
coun
try ta
kes
lead
ersh
ip in
the
deve
lopm
ent a
t GIF
, an
d he
nce,
it is
un
likel
y to
bre
ak
thro
ugh
deci
sive
pr
oble
ms
for t
he
conc
eptu
al
appl
icab
ility.
Pos
sibl
e to
ant
icip
ate
inte
rnat
iona
l co
oper
atio
n.
Hav
ing
a po
ssib
ility
of
beco
min
g an
in
tern
atio
nal s
tand
ard
conc
ept.
Whe
n de
cisi
ve
prob
lem
s fo
r ap
plic
abili
ty a
re
solv
ed, i
t is
poss
ible
to
enh
ance
the
tech
nica
l fea
sibi
lity.
Pos
sibl
e to
ant
icip
ate
inte
rnat
iona
l coo
pera
tion.
Act
ivel
y st
udie
d at
GIF
, an
d ha
ving
a p
ossi
bilit
y of
be
com
ing
an in
tern
atio
nal
stan
dard
con
cept
. B
reak
thro
ugh
on
inno
vativ
e te
chno
logi
es
and
effic
ient
dev
elop
men
t by
sha
ring
role
s ca
n be
ex
pect
ed.
Hav
ing
conc
erns
with
an
ticip
atin
g th
e fe
asib
ility
, bu
t the
y ar
e lim
ited
to th
e on
es o
n co
re a
nd fu
el
rela
ted
issu
es.
To a
ntic
ipat
e th
e fe
asib
ility
, it i
s ne
cess
ary
to s
olve
pr
oble
ms
that
will
det
erm
ine
the
conc
eptu
al
appl
icab
ility.
Pos
sibl
e to
ant
icip
ate
the
feas
ibili
ty w
ith a
hig
h de
gree
of r
elia
bilit
y be
caus
e de
velo
pmen
t su
bjec
ts a
re c
lear
and
al
tern
ativ
e te
chno
logi
es c
an
be p
repa
red.
Tech
nica
l fe
asib
ility
(Inte
rnat
iona
l vi
ewpo
int)
Bot
h th
e ef
ficie
nt u
tiliz
atio
n of
nuc
lear
fuel
reso
urce
s an
d th
e re
duct
ion
of
envi
ronm
enta
l bur
den
are
limite
d.H
avin
g th
e po
tent
ial o
f m
eetin
g th
e ot
her d
esig
n re
quire
men
ts.
Hav
ing
the
pote
ntia
l of
mee
ting
all t
he d
esig
n re
quire
men
ts.
Hav
ing
the
pote
ntia
l of
mee
ting
all t
he d
esig
n re
quire
men
ts, a
s w
ell
as a
ttrac
tiven
ess
as a
hi
gh te
mpe
ratu
re h
eat
sour
ce.
Hav
ing
the
high
leve
l po
tent
ial o
f mee
ting
all t
he
desi
gn re
quire
men
ts.
Whe
n ad
optin
g m
etal
lic fu
el,
furth
er im
prov
emen
t of t
he
core
per
form
ance
can
be
expe
cted
.
Pote
ntia
l co
nfor
mity
to
desi
gn
requ
irem
ents
Wat
er-c
oole
d re
acto
rLe
ad-b
ism
uth-
cool
ed
reac
tor
Hel
ium
gas
-coo
led
reac
tor
Sodi
um-c
oole
d re
acto
rR
eact
or ty
pe
Eval
uatio
n ite
m
Tabl
e 2
Tec
hnic
al s
umm
ary
resu
lts fo
r can
dida
te c
once
pts
for F
Rsy
stem
- 15 -
Pos
sibl
e to
ant
icip
ate
inte
rnat
iona
l co
oper
atio
n.
Rel
ated
inve
stig
atio
ns
in h
ot la
bora
torie
s ar
e co
nduc
ted
in R
ussi
a.
Diff
icul
t to
antic
ipat
e in
tern
atio
nal
coop
erat
ion.
No
coun
try a
ctiv
ely
prom
otes
the
deve
lopm
ent
Pos
sibl
e to
ant
icip
ate
inte
rnat
iona
l coo
pera
tion.
Rel
ated
inve
stig
atio
ns in
ho
t lab
orat
orie
s ar
e co
nduc
ted
in th
e U
SA
.
Pos
sibl
e to
ant
icip
ate
inte
rnat
iona
l coo
pera
tion.
Rel
ated
inve
stig
atio
ns in
hot
la
bora
torie
s ar
e co
nduc
ted
in F
ranc
e, e
tc.
Hav
ing
num
bers
of
tech
nica
l pro
blem
s an
d re
quire
s a
long
tim
e fo
r th
e de
velo
pmen
t
Pos
sibl
e to
ant
icip
ate
the
feas
ibili
ty.
Pos
sibl
e to
ant
icip
ate
the
feas
ibili
ty;
How
ever
, it i
s es
timat
ed
to ta
ke a
rela
tivel
y lo
ng
time
beca
use
infra
stru
ctur
es a
re
requ
ired
to b
e de
velo
ped.
Pos
sibl
e to
ant
icip
ate
the
feas
ibili
ty.
Tech
nica
l fe
asib
ility
(Inte
rnat
iona
l vi
ewpo
int)
Hav
ing
the
pote
ntia
l of
mee
ting
all t
he d
esig
n re
quire
men
ts.
Hav
ing
the
pote
ntia
l of
mee
ting
all t
he d
esig
n re
quire
men
ts.
Hav
ing
the
pote
ntia
l of
mee
ting
all t
he d
esig
n re
quire
men
ts, a
s w
ell a
s sh
owin
g be
tter e
cono
my
of s
mal
l-sca
le fa
cilit
y.
Hav
ing
the
high
leve
l po
tent
ial o
f mee
ting
all t
he
desi
gn re
quire
men
ts, a
nd in
pa
rticu
lar,
show
ing
bette
r ec
onom
y of
larg
e-sc
ale
faci
lity
due
to s
cale
effe
cts.
Pote
ntia
l co
nfor
mity
to
desi
gn
requ
irem
ents
Oxi
de e
lect
row
inni
ngre
proc
essi
ng &
Vi
brat
ion
pack
ing
fuel
fabr
icat
ion
Adv
ance
d aq
ueou
s re
proc
essi
ng &
Vi
brat
ion
pack
ing
fuel
fa
bric
atio
n(*
)
Met
al e
lect
rore
finin
gre
proc
essi
ng &
In
ject
ion
cast
ing
fuel
fa
bric
atio
n
Adv
ance
d aq
ueou
s re
proc
essi
ng &
Sim
plifi
ed
pelle
tizin
gfu
el fa
bric
atio
n
Com
bina
tion
Eval
uatio
n ite
m
Tabl
e 3
Tec
hnic
al s
umm
ary
resu
lts fo
r can
dida
te c
once
pts
for f
uel c
ycle
sys
tem
(*):
The
“gel
atio
npr
oces
s”, a
sub
proc
ess
of th
is v
ibra
tion
pack
ing
proc
ess,
is u
sed
for m
anuf
actu
ring
the
nitri
deco
ated
par
ticle
fuel
for
the
heliu
m g
as-c
oole
d re
acto
r; ho
wev
er, t
he d
evel
opm
ent o
f the
cor
resp
ondi
ng fu
el c
ycle
con
cept
is c
onsi
dere
d to
be
mor
e ef
ficie
nt
to in
itiat
e af
ter t
he n
itrid
e co
ated
par
ticle
fuel
con
cept
wou
ldbe
est
ablis
hed
by th
e pr
ogre
ss o
f the
FR
sys
tem
dev
elop
men
t.
- 16 -
Figu
re 1
Con
cept
of t
he s
odiu
m-c
oole
d re
acto
r
OD
S s
teel
cla
ddin
g tu
be fo
r hig
h bu
rnup
Pre
vent
ion
of s
odiu
m
chem
ical
reac
tion
•C
ompl
ete
adop
tion
of a
do
uble
-wal
led
pipi
ng s
yste
m
•S
team
gen
erat
or w
ith s
traig
ht
doub
le-w
alle
d he
at tr
ansf
er
tube In
spec
tion
and
repa
ir te
chno
logy
und
er s
odiu
m
Enh
ance
men
t of r
eact
or
core
saf
ety
•P
assi
ve re
acto
r shu
tdow
n sy
stem
and
dec
ay h
eat
rem
oval
by
natu
ral c
ircul
atio
n
•R
ecrit
ical
ityfre
e co
re c
once
pt
durin
g se
vere
cor
e da
mag
e
Sec
onda
ry p
ump
Ste
am g
ener
ator Inte
grat
ed in
term
edia
te
heat
exc
hang
er
with
prim
ary
pum
p
Rea
ctor
ves
sel
Red
uctio
n in
mat
eria
l am
ount
an
d bu
ildin
g vo
lum
e th
roug
h th
e ad
optio
n of
inno
vativ
e te
chno
logi
es
•2-lo
op a
rrang
emen
t for
a
sim
plifi
ed p
lant
sys
tem
•Hig
h-ch
rom
ium
ste
el
stru
ctur
al m
ater
ial f
or a
sh
orte
ned
pipi
ng le
ngth
•Int
egra
ted
inte
rmed
iate
hea
t ex
chan
ger w
ith p
rimar
y pu
mp
for a
sim
plifi
ed p
rimar
y co
olin
g sy
stem
•Com
pact
reac
tor v
esse
l
- 17 -
Figu
re 2
Con
cept
of t
he c
ombi
natio
n of
the
adva
nced
aqu
eous
repr
oces
sing
sy
stem
and
the
sim
plifi
ed p
elle
tizin
gfu
el fa
bric
atio
n sy
stem
U c
ryst
alliz
atio
n pr
oces
s th
at c
an d
ram
atic
ally
redu
ce
the
extr
actio
n pr
oces
s flo
w
Sing
le c
ycle
co-
extr
actio
n of
U, P
u an
d N
pw
ith lo
w
deco
ntam
inat
ion
No
Purif
icat
ion
proc
esse
s of
U
and
Pu b
ecau
se th
e re
cove
ry in
lo
w-d
econ
tam
inat
ion
proc
ess
is p
erm
itted
.
MA
reco
very
by
usin
g ex
trac
tion
chro
mat
ogra
phy
that
allo
ws
the
use
of c
ompa
ct c
ompo
nent
s an
d a
low
er a
mou
nt o
f sec
onda
ry
was
te
Die
lubr
icat
ing-
type
m
oldi
ng w
ithou
t lub
rican
t-m
ixin
g
Adj
ustm
ent o
f Pu
cont
ent a
t so
lutio
n st
ate
is e
nabl
ed b
y in
tegr
atin
g re
proc
essi
ng
and
fuel
fabr
icat
ion
plan
t
Dis
asse
mbl
ing
and
Shea
ring Dis
solu
tion
Cry
stal
lizat
ion
Co-
extra
ctio
n
Pin
fabr
icat
ion
and
asse
mbl
y of
bun
dle
MA
reco
very
by
extra
ctio
n ch
rom
atog
raph
y
Adju
stm
ent o
f Pu
cont
ent
Hig
h-le
vel
liqui
d w
aste
Den
itrat
ion,
Cal
cina
tion
& R
educ
tion,
Gra
nula
tion
Mol
ding
and
Sin
terin
g
In-c
ell f
uel f
abric
atio
n en
ablin
g lo
w d
econ
tam
inat
ion
and
MA
re
cycl
e
Pow
der m
ixin
g pr
oces
s is
re
mov
ed b
y ad
just
ing
Pu
cont
ent a
t sol
utio
nst
ate
- 18 -
Figu
re 3
R&
D p
rosp
ects
unt
il ap
prox
imat
ely
2015
(*) I
nves
tigat
ion
will
als
o be
per
form
ed o
n th
e R
&D
str
ateg
y fo
r the
com
plem
enta
ry c
once
pts
and
the
nece
ssity
of i
ntro
duci
ng b
asic
tech
nolo
gies
.
C&
R
Inte
rim s
umm
ary
C&
R
Obt
aine
d re
sults
・Se
lect
ion
of p
rom
isin
g co
ncep
ts a
nd
prin
cipl
es fo
r R&
D
prio
ritiz
atio
n
・R
&D
pro
gram
unt
il ap
prox
imat
ely
201
5 an
d th
e fu
ture
issu
es
Phas
e II
Phas
e IV
Item
s to
be
perf
orm
ed・
Elem
enta
l exp
erim
ents
and
rese
arch
on
the
adop
ted
inno
vativ
e te
chno
logi
es・O
ptim
izat
ion
stud
y on
the
conc
eptu
al d
esig
n of
an
inno
vativ
e pl
ant(*
)
2005
~ 20
1520
10
Phas
e III
Expe
cted
resu
lts・
Det
erm
inat
ion
of in
nova
tive
tech
nolo
gies
to b
e ad
opte
d.・Es
tabl
ishm
ent o
f com
mer
cial
(rea
ctor
an
d cy
cle)
con
cept
s th
at e
xcel
in
econ
omy,
mai
ntai
nabi
lity
and
repa
irabi
lity,
etc
.
Item
s to
be
perf
orm
ed・
Elem
enta
l exp
erim
ents
and
rese
arch
ai
min
g at
the
eval
uatio
n of
the
appl
icab
ility
of i
nnov
ativ
e te
chno
logi
es・C
once
ptua
l des
ign
stud
y on
an
inno
vativ
e pl
ant s
yste
m(*
)
Expe
cted
resu
lts・Pr
esen
tatio
n of
a c
omm
erci
aliz
atio
n im
age
(incl
udin
g m
aint
aina
bilit
y an
d re
paira
bilit
y)・D
evel
opm
ent o
f dec
isiv
e da
ta fo
r the
ap
plic
abili
ty o
f com
mer
cial
pla
nts
base
d on
el
emen
tal e
xper
imen
t res
ults
, etc
.・Pr
esen
tatio
n of
the
tech
nica
l spe
cific
atio
n of
co
mm
erci
al p
lant
s.
・Pr
esen
tatio
n of
an
R&
D p
rogr
am le
adin
g to
com
mer
cial
izat
ion
The
1st s
tage
(Dev
elop
men
t of t
echn
ical
sch
emes
)
Inte
rim s
umm
ary
C&
R
- 19 -
Dem
onst
ratio
n of
inno
vativ
e te
chno
logi
es
Gai
ning
a c
lear
vie
w o
f the
ac
hiev
emen
t of a
n in
nova
tive
tech
nolo
gy d
emon
stra
tion
and
deve
lopm
ent g
oals
Test
s an
d op
erat
ions
usi
ng
the
dem
onst
ratio
n te
st
faci
lity
(Rea
ctor
and
Fue
l cy
cle)
Pro
mot
ion
of d
emon
stra
tion
Con
firm
atio
n of
the
achi
evem
ent o
f dev
elop
men
t go
als C
onfir
mat
ion
of
econ
omy
and
relia
bilit
y as
com
mer
cial
faci
litie
s
The
1st s
tage
Th
e 2n
d st
age
The
3rd
stag
e
Initiating introduction of commercial facilities
Initiation of full-scale introduction on a commercial basis.
（~
2015
）（~
2050
）
Level at which demonstration test can be started.
Dev
elop
men
t of t
echn
ical
sc
hem
es
Dev
elop
men
t of d
ecis
ive
data
for
appl
icab
ility
of c
omm
erci
al
faci
litie
sR
&D
of e
lem
enta
l te
chno
logi
es o
n in
nova
tive
tech
nolo
gies
Pre
sent
atio
n of
the
com
mer
cial
izat
ion
imag
eC
once
ptua
l des
ign
stud
y by
re
flect
ing
the
expe
rimen
tal
data
on
elem
enta
l tec
hnol
ogie
sP
rese
ntat
ion
of a
n R
&D p
rogr
am
lead
ing
to c
omm
erci
aliz
atio
nC
ondu
ctio
n of
des
ign
stud
y of
th
e de
mon
stra
tion
test
faci
lity
and
spec
ifica
tion
of th
e te
st
cont
ents
Figu
re 4
Im
age
of th
e st
aged
R&
D u
ntil
appr
oxim
atel
y 20
50
Elem
enta
l exp
erim
ent s
cale
Scal
e on
whi
ch a
per
spec
tive
of
com
mer
cial
izat
ion
can
be g
aine
dC
omm
erci
al s
cale
- 20 -
Not
yet
stu
died
.
Can
acc
ept M
A c
onte
nt u
p to
ap
prox
. 4%
und
er lo
w
deco
ntam
inat
ion
cond
ition
121
GW
d/t
35%
/ 3%
38%
/ 3%
47%
/ 3%
42.5
% /
4%Th
erm
al e
ffici
ency
/ Ons
ite
load
fact
or
App
rox.
93%
App
rox.
93%
App
rox.
92%
App
rox.
95(9
4)%
App
rox.
95(9
4)%
Ava
ilabi
lity
(Cal
cula
ted
valu
e)(9
0%or
mor
e)
18m
onth
s
128
GW
d/t
155
GW
d/t
－5.9
t/GW
e
1.04
Bre
ak-e
ven
core
18m
onth
s
89G
Wd/
t
123
GW
d/t
－7.0
t/GW
e
1.03
Bre
ak-e
ven
core
26(2
2)m
onth
s
115
(153
)G
Wd/
t
150
(153
)G
Wd/
t
－
5.8
(5.1
)t/G
We
1.03
(1.0
3)
Bre
ak-e
ven
core
Who
le-c
ore
aver
age
(60G
Wd/
t or h
ighe
r)
In-c
ore
aver
age
(150
GW
d/t o
r hig
her)
45G
Wd/
t10
5G
Wd/
t69
GW
d/t
90(1
34)
GW
d/t
Uni
t con
stru
ctio
n co
st
(¥20
0,00
0/kW
eor
less
)
Rea
ctor
out
let t
empe
ratu
re
Ope
ratio
n pe
riod
(18
mon
ths
or lo
nger
)
b)
e)R
elat
ive
valu
e ：A
ppro
x. 1
00％
Rel
ativ
e va
lue ：
App
rox.
100
％R
elat
ive
valu
e ：A
ppro
x. 1
00％
Rel
ativ
e va
lue ：
App
rox.
90 ％
18m
onth
s18
mon
ths
18m
onth
s26
(22)
mon
ths
c)
287℃
445℃
850℃
550℃
d)
Hav
ing
a po
ssib
ility
of tr
ansm
utin
g se
lf-ge
nera
ting
LLFP
(129 I
and
99Tc
), by
inst
allin
g th
e FP
bot
h in
side
the
core
an
d th
e ra
dial
bla
nket
regi
on.
FP tr
ansm
utat
ion
Tim
e re
quire
d to
repl
ace
all n
ucle
ar
pow
er re
acto
rs w
ith F
Rs
Fiss
ile fu
el in
vent
ory
requ
ired
for
the
initi
al lo
adin
g co
re
a)MA
bur
ning
Bre
edin
g ra
tio(1
.0～
appr
ox. 1
.2)
App
rox
250
year
sA
ppro
x. 7
0 ye
ars
App
rox.
110
ye
ars
App
rox.
60
year
s
App
rox.
11t/G
We
5.9
t/GW
e7.
0t/G
We
5.7
(4.9
)t/G
We
-B
reed
ing
core
Bre
edin
g co
reB
reed
ing
core
88G
Wd/
t15
4G
Wd/
t14
7(1
49)
GW
d/t
Econ
omic
co
mpe
ti-tiv
enes
s
Can
acc
ept M
A c
onte
nt u
p to
app
rox.
5%
that
is re
cycl
ed fr
om L
WR
spen
t fue
l und
er lo
w d
econ
tam
inat
ion
cond
ition
(with
FP
con
tent
of 0
.2 v
ol%
).R
educ
tion
ofen
viro
n-m
enta
l bu
rden
1.05
1.10
1.11
1.10
(1.1
1)Ef
ficie
nt
utili
zatio
n of
nuc
lear
fu
el
reso
urce
s
Hav
ing
a po
ssib
ility
of a
void
ing
recr
itica
lity
by in
stal
ling
abso
rber
, etc
.
Hav
ing
a po
ssib
ility
of a
void
ing
recr
itica
lity
due
to fu
el fl
oatin
g
Hav
ing
a po
ssib
ility
of a
void
ing
recr
itica
lity
by fu
el e
xpul
sion
ca
used
by
in-c
ore
heat
ing
and
pres
suriz
atio
n, a
s w
ell a
s in
stal
latio
n of
the
core
cat
cher
.
Out
-of-p
ile a
nd in
-pile
exp
erim
ents
ar
e un
derw
ay, c
once
rnin
g th
e pa
ssiv
e sa
fety
mec
hani
sm a
nd
mea
sure
s to
avo
id re
criti
calit
y.
Safe
ty
Wat
er-c
oole
d re
acto
r(1
,356
MW
e)M
OX
fuel
Pb-B
i-coo
led
reac
tor
(750
MW
e)N
itrid
e fu
el
Hel
ium
gas
-coo
led
reac
tor
(1,5
00M
We)
Nitr
ide
fuel
Sodi
um-c
oole
d re
acto
r (1
,500
MW
e)M
OX
fuel
(met
allic
fuel
)D
esig
n re
quire
men
t
Ref
eren
ce T
able
1 P
oten
tial c
onfo
rmity
to d
esig
n re
quire
men
ts o
f eac
h FR
sys
tem
a) F
uel c
ost r
educ
tion
b)
Fuel
burn
upc)
Ava
ilabi
lity
impr
ovem
ent
d) T
herm
al e
ffici
ency
impr
ovem
ent
e) C
apita
l cos
t red
uctio
n*
Ava
ilabi
lity
(des
ign
valu
e) =
100
×op
erat
ion
perio
d／(o
pera
tion
perio
d +
plan
ned
outa
ge p
erio
d）B
reed
ing
core
: Cor
e sp
ecifi
catio
n w
hich
redu
ces
the
doub
ling
time
to b
reed
Pu
mor
e ef
ficie
ntly
. B
reak
-eve
n co
re: C
ore
spec
ifica
tion
whi
ch a
ims
to re
duce
the
fuel
cyc
le c
ost b
y im
prov
ing
aver
aged
fuel
bur
nup.
- 21 -
Bre
ak-e
ven
core
App
rox.
95%
App
rox.
115
%A
ppro
x. 9
0%A
ppro
x. 1
00%
App
rox.
100
%（
App
rox.
95%
）
App
rox.
125
%（
App
rox.
115
%）
Smal
l-sca
le p
lant
[50t
/y]
(Sup
ercr
itica
l dire
ct
extra
ctio
n pr
oces
s ）
App
rox.
110
%
App
rox.
90%
App
rox.
75%
App
rox.
95%
App
rox.
65%
Bre
ak-e
ven
core
App
rox.
80%
App
rox.
140
%
App
rox.
75%
App
rox.
55%
Bre
ak-e
ven
core
App
rox.
60%
App
rox.
95%
（A
ppro
x. 9
0%）
App
rox.
105
%（
App
rox.
95%
）
App
rox.
45%
Bre
ak-e
ven
core
Ass
urin
g di
fficu
lty in
acc
essi
bilit
y by
low
dec
onta
min
atio
nA
ssur
ing
diffi
culty
in
acce
ssib
ility
App
rox.
60%
App
rox.
85%
App
rox.
35%
App
rox.
85%
Amou
nt o
f TR
U
and
high
β/ γ
was
tes ≦
1.6L
/GW
h
Vol
ume
of H
LW≦
0.5L
/GW
h
Pre
vent
ion
of p
ure
Pu
hand
ling
Rec
over
y ra
tio o
f U a
ndTR
U ≧
99%
App
rox.
110
%A
ppro
x. 8
0%A
ppro
x. 1
35%
（A
ppro
x. 1
20%）
Smal
l-sca
le p
lant
[50t
/y]
(Sup
ercr
itica
l dire
ct
extra
ctio
n pr
oces
s ）
c)b)
App
rox.
85%
App
rox.
85%
App
rox.
70%
Larg
e-sc
ale
plan
t [2
00t/y
]
App
rox.
120
%A
ppro
x. 1
00%
App
rox.
145
%A
ppro
x. 1
00%
（A
ppro
x. 9
5%）
Larg
e-sc
ale
and
smal
l-sc
ale
plan
ts(S
uper
criti
cal d
irect
extra
ctio
n pr
oces
s ）
Larg
e-sc
ale
plan
t [2
00t/y
]a)
Bre
edin
g co
reB
reed
ing
core
Bre
edin
g co
reB
reed
ing
core
Co-
reco
very
of U
and
Pu
Co-
reco
very
of U
, P
u an
d N
pC
o-re
cove
ry o
f U a
nd T
RU
Co-
reco
very
of U
, P
u an
d N
pEn
hanc
e-m
ento
f nu
clea
r no
n-pr
olife
-ra
tion
Pho
spha
te g
lass
, Allo
y:A
ppro
x. 8
0%B
oros
ilicat
e gl
ass:
App
rox.
60%
Gla
ss-b
onde
d so
dalit
e:A
ppro
x. 1
10%
Bor
osilic
ate
glas
s:A
ppro
x. 6
0%R
educ
tion
of e
nviro
n-m
enta
l bu
rden
Pos
sibl
e to
be
desi
gned
.(C
onfir
mat
ion
of th
e M
A re
cove
ry
ratio
is re
quire
d.A
des
ign
that
can
reco
ver 9
9% o
r mor
e of
U a
nd T
RU
is e
stim
ated
to b
e po
ssib
le b
y ba
sic
test
dat
a.
Effic
ient
ut
iliza
tion
of n
ucle
ar
fuel
re
sour
ces
App
rox.
80%
App
rox.
65%
App
rox.
60%
Pot
entia
l to
mee
t des
ign
requ
irem
ents
.（
Des
ign
that
co
nsid
ers
treat
men
t of c
hlor
ine
gas,
hi
gh-te
mpe
ratu
re m
elt,
activ
e m
etal
, et
c.）
Pot
entia
l to
mee
t des
ign
requ
irem
ents
. (C
an fo
llow
exi
stin
g gu
idel
ines
, etc
.)
Pot
entia
l to
mee
t des
ign
requ
irem
ents
. (D
esig
n th
at c
onsi
ders
trea
tmen
t of
high
-tem
pera
ture
mel
t, ac
tive
met
al,
etc.
, as
wel
l as
the
criti
calit
y co
ntro
l by
com
bini
ng th
e m
ass
cont
rol a
nd
chem
ical
form
con
trol ）
Pot
entia
l to
mee
t des
ign
requ
irem
ents
. (C
an fo
llow
exi
stin
g gu
idel
ines
, etc
.)※
Sup
ercr
itica
l dire
ct e
xtra
ctio
n pr
oces
s ne
eds
a de
sign
con
side
ring
the
treat
men
t of h
igh-
pres
sure
flui
d to
ha
ve a
pot
entia
l con
form
ity to
des
ign
requ
irem
ents
.
Safe
ty
Oxi
de e
lect
row
inni
ngre
proc
essi
ng
+Vi
brat
ion
pack
ing
fuel
fa
bric
atio
n (V
ipac
)(M
OX
fuel
)
Adv
ance
d aq
ueou
s re
proc
essi
ng＋
Vibr
atio
n pa
ckin
g fu
el
fabr
icat
ion
(Sph
ere-
pack
) (M
OX
fuel
)
Met
al e
lect
rore
finin
gre
proc
essi
ng
+In
ject
ion
cast
ing
fuel
fa
bric
atio
n(M
etal
lic fu
el)
Des
ign
requ
irem
ent
Adv
ance
d aq
ueou
s re
proc
essi
ng+
Sim
plifi
ed p
elle
tizin
gfu
el
fabr
icat
ion
(MO
X fu
el)
Des
ign
requ
irem
ent
Ref
eren
ce T
able
2 P
oten
tial c
onfo
rmity
to d
esig
n re
quire
men
ts o
f eac
h fu
el c
ycle
sys
tem
a) (R
epro
cess
ing
+ Fu
el fa
bric
atio
n) c
ost ≦
¥0.8
/kW
hb)
Tra
nspo
rtatio
n/St
orag
e/W
aste
dis
posa
l cos
t ≦¥0
.3/k
Wh
c) F
uel c
ycle
cos
t ≦¥1
.1/k
Wh
Economic competitiveness
Reprocessing
- 22 -
Bur
nup
Whe
n co
mpa
red
with
LW
Rs,
hig
her b
reed
ing
ratio
is a
chie
vabl
e un
der
equi
vale
nt b
urnu
p.
~ 22
mon
ths
55 G
Wd/
t
96 G
Wd/
t
3.9t
/GW
e
1.26
~ 22
(18)
mon
ths
~ 22
(26)
mon
ths
~ 22
(26)
mon
ths
Ope
ratio
n pe
riod
The
who
le-c
ore-
aver
aged
bu
rnup
is h
ighe
r tha
n th
at
of M
OX
fuel
led
core
by
appr
oxim
atel
y 50
%.
134
(90)
GW
d/t
149
(147
) GW
d/t
4.9
(5.7
) t/G
We
1.11
(1.1
0)
The
who
le-c
ore-
aver
aged
bu
rnup
is h
ighe
r tha
n th
at o
f M
OX
fuel
led
core
by
appr
oxim
atel
y 30
%.
153
(115
) GW
d/t
153
(150
) GW
d/t
5.1
(5.8
)t/G
We
1.03
(1.0
3)
The
who
le-c
ore-
aver
aged
bu
rnup
is h
ighe
r tha
n th
at o
f M
OX
fuel
led
core
by
appr
oxim
atel
y 20
%.
Feat
ure
3.9
(4.4
)t/G
We
Fiss
ile fu
el a
mou
nt re
quire
d fo
r the
in
itial
load
ing
core
95 (1
54) G
Wd/
tA
vera
ge in
the
core
fuel
re
gion
1.19
(1.2
0)B
reed
ing
ratio
65 (5
5) G
Wd/
tA
vera
ge in
the
who
le c
ore
(incl
udin
g th
e bl
anke
t re
gion
)
○M
etal
lic-fu
elle
d co
res
(Des
ign
cond
ition
: Rea
ctor
out
let t
empe
ratu
re=5
50℃
, Ope
ratio
n pe
riod
=22
mon
ths)
can
・ac
hiev
e a
bree
ding
ratio
of a
ppro
x. 1
.26
at m
axim
um (a
ppro
x. 1
.20
for M
OX-
fuel
led
core
s) u
nder
bur
nup
equi
vale
nt to
LW
Rs.
(It i
s ne
cess
ary
to c
onfir
m th
e ap
plic
abili
ty o
f suc
h th
erm
al d
esig
ns in
the
futu
re.)
・im
prov
e bu
rnup
by 2
0-50
% c
ompa
red
with
thos
e of
MO
X-fu
elle
d co
res
unde
r the
bre
edin
g ra
tio o
f app
rox.
1.2
0 or
bel
ow,
as w
ell a
s de
crea
se th
e in
itial
ly-lo
adin
g fis
sile
fuel
am
ount
by
10%
or m
ore.
Valu
es in
( )
are
est
imat
ed o
n M
OX
-fuel
led
core
s.(D
esig
n co
nditi
on o
f the
reac
tor o
utle
t tem
pera
ture
is 5
50℃
.)
Ref
eren
ce T
able
3 I
mpr
ovem
ent i
n co
re p
erfo
rman
ce b
y th
e em
ploy
men
t of m
etal
lic fu
el
○It
is e
stim
ated
by
alo
ng-te
rm m
ass
flow
anal
ysis
on
the
tran
sitio
n in
to th
e FR
era
that
, for
inst
ance
, ass
umin
g th
e in
itiat
ion
ofFR
intr
oduc
tion
in 2
030,
met
allic
-fuel
led
core
(bre
edin
g ra
tio o
f 1.2
6) c
an re
duce
the
cum
ulat
ive
dem
and
amou
nt o
f nat
ural
ura
nium
by
appr
ox. 2
0% c
ompa
red
with
MO
X-fu
elle
d co
re (b
reed
ing
ratio
of 1
.20)
.
- 23 -
－－
Met
al
elec
trore
finin
g
－－
－O
xide
el
ectro
win
ning
－A
dvan
ced
aque
ous
Coa
ted
parti
cle
Inje
ctio
n ca
stin
gV
ibra
tion
pack
ing
Sim
plifi
ed
pelle
tizin
g
Fuel
fabr
icat
ion
syst
emR
epro
cess
ing
syst
em
O Na
WH
eP
b
N
M
N
Na
PbN
To b
e ap
plic
able
by
addi
ng p
roce
sses
in
clud
ing
15N
-enr
iche
d ni
troge
nre
cove
ry a
nd n
itrid
ing
proc
esse
s
NO M
Na WHe
Pb
Met
allic
fuel
Nitr
ide
fuel
Oxi
de fu
el (M
OX
fuel
)S
odiu
m-c
oole
d re
acto
r
Hel
ium
gas
-coo
led
reac
tor
Lead
-Bis
mut
h-co
oled
reac
tor
Wat
er-c
oole
d re
acto
r
Ref
eren
ceTa
ble
4C
ombi
natio
ns o
f the
repr
oces
sing
and
fuel
fabr
icat
ion
syst
ems
as w
ell a
s th
e FR
syst
ems
and
the
corre
spon
ding
fu
el ty
pes,
on
whi
ch P
hase
II s
tudi
es w
ere
perfo
rmed
.
OO Na O Na
- 24 -
Low
de
cont
amin
ated
TR
U fu
el c
ycle
Co-
reco
very
of U
, Pu
and
Np
Appr
ox. 6
% o
f co
nven
tiona
l res
ourc
es
of n
atur
al u
rani
um
・Am
ount
of H
LW0.
9 (r
elat
ive
valu
e）(*
2)
・Am
ount
of L
LW2.
1 (r
elat
ive
valu
e）(*
2)
・Po
tent
ial h
azar
d du
e to
ra
dioa
ctiv
ity (1
000
year
s la
ter)
1.4
(rel
ativ
e va
lue）
(*2)
・Po
ssib
le to
acc
ept M
A fro
m
LWR
s
Appr
ox. 7
0%(*
1)
Pers
pect
ive
of
assu
ring
safe
ty
agai
nst d
esig
n ba
sis
even
ts, a
s w
ell a
s be
yond
de
sign
bas
is
acci
dent
s is
co
nfirm
ed.
Adv
ance
d aq
ueou
s re
proc
essi
ng ＋
Coa
ted
part
icle
fu
el fa
bric
atio
n (S
pher
e-pa
ck)
Hel
ium
gas
-co
oled
re
acto
r(N
itrid
e co
ated
pa
rtic
le fu
el)
(3)
Low
de
cont
amin
ated
TR
U fu
el c
ycle
Co-
reco
very
of U
an
d TR
U
Appr
ox. 5
% o
f co
nven
tiona
l res
ourc
es
of n
atur
al u
rani
um
・Am
ount
of H
LW
1.7
(rel
ativ
e va
lue）
(*2)
・Am
ount
of L
LW1.
0 (r
elat
ive
valu
e）(*
2)
・Po
tent
ial h
azar
d du
e to
radi
oact
ivity
(100
0 ye
ars
late
r)2.
1 (r
elat
ive
valu
e）(*
2)
・Po
ssib
le to
acc
ept M
A fro
m
LWR
s
Appr
ox. 7
0%(*
1)
Pers
pect
ive
of
assu
ring
safe
ty
agai
nst d
esig
n ba
sis
even
ts, a
s w
ell a
s be
yond
de
sign
bas
is
acci
dent
s is
co
nfirm
ed.
Met
al
elec
tror
efin
ing
repr
oces
sing
＋
Inje
ctio
n ca
stin
g fu
el fa
bric
atio
n
Sodi
um-
cool
ed
reac
tor
(Met
allic
fuel
)
(2)
Low
de
cont
amin
ated
TR
U fu
el c
ycle
Co-
reco
very
of U
, Pu
and
Np.
Appr
ox. 5
% o
f co
nven
tiona
l res
ourc
es
of n
atur
al u
rani
um
・Am
ount
of H
LW1.
0 (r
elat
ive
valu
e）(*
2)
・Am
ount
of L
LW1.
0 (r
elat
ive
valu
e）(*
2)
・Po
tent
ial h
azar
d du
e to
ra
dioa
ctiv
ity (1
000
year
s la
ter)
1.0
(rel
ativ
e va
lue）
(*2)
・Po
ssib
le to
acc
ept M
A fro
m
LWR
s
Appr
ox. 6
0%(*
1)
Pers
pect
ive
of
assu
ring
safe
ty
agai
nst d
esig
n ba
sis
even
ts, a
s w
ell a
s be
yond
de
sign
bas
is
acci
dent
s is
co
nfirm
ed.
Adv
ance
d aq
ueou
s re
proc
essi
ng＋
Sim
plifi
ed
pelle
tizin
gfu
el
fabr
icat
ion
Sodi
um-
cool
ed
reac
tor
(MO
Xfu
el)
(1)
Enha
ncem
ent
of n
ucle
ar
non-
prol
ifera
tion
Effic
ient
util
izat
ion
of
nucl
ear f
uel r
esou
rces
(c
umul
ativ
e de
man
d am
ount
of n
atur
al
uran
ium
up
to th
e co
mpl
etio
n of
tra
nsiti
on
from
LW
Rs
to F
BRs)
Red
uctio
n of
env
ironm
enta
l bu
rden
(R
educ
tion
in ra
dioa
ctiv
e w
aste
am
ount
s an
d th
e po
tent
ial h
azar
d du
e to
radi
oact
ivity
(100
0 ye
ars
late
r), a
s w
ell a
s ac
cept
abili
ty o
f M
A fro
m L
WR
s)
Econ
omic
co
mpe
titiv
enes
s (P
ower
gen
erat
ing
cost
is e
qual
to o
r lo
wer
than
that
of
futu
re L
WR
s.)
Safe
tyFu
el c
ycle
sy
stem
FR s
yste
m
Pote
ntia
l con
form
ity to
des
ign
requ
irem
ents
Stud
ied
conc
ept
*1: R
elat
ive
perc
enta
ge to
a p
ower
gen
erat
ing
cost
of f
utur
e LW
Rs
. (Br
eedi
ng c
ore)
*2: R
elat
ive
valu
es c
alcu
late
d by
ass
umin
g th
e w
aste
am
ount
s an
dpo
tent
ial h
azar
d du
e to
radi
oact
ivity
of (
a) b
e 1.
Ref
eren
ce T
able
5 P
oten
tial c
onfo
rmity
to d
esig
n re
quire
men
ts a
s th
e en
tire
FR c
ycle
sys
tem
- 25 -
Ref
eren
ce F
igur
e 1
Tec
hnic
al fe
asib
ility
of e
ach
FR s
yste
m
Cla
ssifi
catio
n of
the
tech
nica
l fea
sibi
lity
(The
hei
ght o
f eac
h hu
rdle
cor
resp
onds
to it
s di
fficu
lty.)
Low
: Inn
ovat
ive
tech
nolo
gies
on
whi
ch c
lear
per
spec
tive
of th
e de
velo
pmen
t is
gain
ed w
ith le
ss u
ncer
tain
ty.
Med
ium
: Inn
ovat
ive
tech
nolo
gies
on
whi
ch e
xist
ing
know
ledg
e is
less
and
the
pers
pect
ive
of th
e de
velo
pmen
t is
som
ewha
t unc
erta
in.
Hig
h: In
nova
tive
tech
nolo
gies
rela
ted
with
the
fuel
and
mat
eria
l, w
hich
hav
e th
e gr
eate
st u
ncer
tain
ty a
nd re
quire
con
side
rabl
e tim
e fo
r R&D
.
・C
ladd
ing
tube
・O
DS
ste
el c
ladd
ing
tube
・M
aint
enan
ce a
nd re
pair
tech
nolo
gies
・St
eam
gen
erat
or・C
oola
nt p
ump
・H
igh-
chro
miu
mst
eel
・3-
dim
ensi
onal
bas
e is
olat
ion
・Sa
fety
tech
nolo
gy: P
assi
ve
safe
ty m
echa
nism
・3-
dim
ensi
onal
bas
e is
olat
ion
・H
eat r
esis
tant
mat
eria
l・S
afet
y te
chno
logy
: Con
tain
men
t fac
ility
・S
afet
y te
chno
logy
: Dec
ay h
eat r
emov
al b
y na
tura
l circ
ulat
ion
・G
as tu
rbin
e・S
afet
y te
chno
logy
: Pas
sive
mec
hani
sm fo
r cea
sing
fis
sion
reac
tion
durin
g co
re d
amag
e・S
afet
y te
chno
logy
: Pas
sive
saf
ety
mec
hani
sm
10 y
ears
late
rE
nd o
f the
Fea
sibi
lity
Stu
dy P
hase
II
Sod
ium
-coo
led
reac
tor
Wat
er-c
oole
d re
acto
r
Lead
-bis
mut
h-co
oled
reac
tor
Hel
ium
gas
-co
oled
reac
tor
Inte
rnat
iona
l coo
pera
tion
can
be e
xpec
ted
on th
e gr
ay-
code
dis
sues
●：Te
chno
logy
hav
ing
anal
tern
ativ
e
●O
DS
ste
el c
ladd
ing
tube
●H
ighl
y re
liabl
e st
eam
gen
erat
or
・N
itrid
e co
ated
par
ticle
fuel
・H
exag
onal
blo
ck-ty
pe fu
el s
ubas
sem
bly
・S
afet
y te
chno
logy
: Pas
sive
mec
hani
sm fo
r cea
sing
fiss
ion
reac
tion
durin
g th
e co
re d
amag
e・C
oola
bilit
yof
the
clos
e-pa
cked
latti
ce c
ore
・M
echa
nica
l val
idity
of t
he fu
el s
ubas
sem
bly
・O
pera
tiona
l con
trol p
erfo
rman
ce
・C
orro
sion
pre
vent
ion
tech
nolo
gy a
nd c
orro
sion
resi
stan
t mat
eria
l・N
itrid
e fu
el・S
afet
y te
chno
logy
: Pas
sive
mec
hani
sm fo
r cea
sing
fiss
ion
reac
tion
durin
gth
e co
re d
amag
e
●R
educ
tion
in th
e pi
ping
leng
th b
y ad
optin
g th
e hi
gh-c
hrom
ium
stee
l●
Inte
gral
inte
rmed
iate
hea
t exc
hang
er w
ith p
rimar
y pu
mp
・M
aint
enan
ce a
nd re
pair
tech
nolo
gies
・S
afet
y te
chno
logy
: Pas
sive
mec
hani
sm fo
r cea
sing
fiss
ion
reac
tion
durin
g co
re d
amag
e
- 26 -
Ref
eren
ce F
igur
e 2
Tec
hnic
al fe
asib
ility
of e
ach
fuel
cyc
le s
yste
m
・M
A re
cove
ry
・D
evel
opm
ent o
f saf
ety
desi
gn
met
hodo
logy
・A
pplic
abilit
y of
pho
spha
te g
lass
vi
trific
atio
n・Fu
el in
spec
tion
tech
nolo
gy
・C
onfir
mat
ion
of T
RU
reco
very
pro
cess
by
usin
g sp
ent f
uel
・C
onfir
mat
ion
of m
anuf
actu
rabi
lity
of lo
w
deco
ntam
inat
ion
MA
-bea
ring
fuel
・R
educ
tion
in H
LWam
ount
・S
afeg
uard
tech
nolo
gy・V
alid
ity o
f MA
reco
very
tech
nolo
gy・Q
ualit
y of
gra
nula
ted
fuel
par
ticle
・C
ryst
alliz
atio
n eq
uipm
ent
・C
ryst
alliz
atio
n / w
ashi
ng e
quip
men
t・E
xtra
ctio
n ch
rom
atog
raph
y eq
uipm
ent
・R
emot
e m
aint
enan
ce a
nd re
pair
tech
nolo
gies
・Fu
el in
spec
tion
tech
nolo
gy
・C
entri
fuga
l ext
ract
or
・D
evel
opm
ent o
f saf
ety
desi
gn m
etho
dolo
gy
Assu
min
g te
chni
cal c
olla
bora
tion
with
the
US
A
Adv
ance
d aq
ueou
s re
proc
essi
ng &
Sim
plifi
ed
pelle
tizin
gfu
el fa
bric
atio
n
Adv
ance
d aq
ueou
s re
proc
essi
ng &
Vib
ratio
n pa
ckin
g fu
el fa
bric
atio
n
Oxi
de e
lect
row
inni
ngre
proc
essi
ng &
Vib
ratio
n pa
ckin
g fu
el fa
bric
atio
n
Met
al e
lect
rore
finin
gre
proc
essi
ng &
Inje
ctio
n ca
stin
g fu
el fa
bric
atio
n ・Im
prov
emen
t in
curre
nt e
ffici
ency
fo
rMO
Xco
depo
sitio
n・R
ecov
ery
ratio
of U
and
TR
U
Cla
ssifi
catio
n of
the
tech
nica
l fea
sibi
lity
(The
hei
ght o
f eac
h hu
rdle
cor
resp
onds
to it
s di
fficu
lty.)
Low
: Inn
ovat
ive
tech
nolo
gies
on
whi
ch a
cle
ar p
ersp
ectiv
e of
the
deve
lopm
ent i
s ga
ined
with
less
unc
erta
inty
. M
ediu
m: I
nnov
ativ
e te
chno
logi
es o
n w
hich
exi
stin
g kn
owle
dge
is le
ss a
nd p
ersp
ectiv
e of
the
deve
lopm
ent i
s so
mew
hat u
ncer
tain
.H
igh:
Inno
vativ
e te
chno
logi
es re
late
d w
ith th
e fu
el a
nd m
ater
ial,
whi
ch h
ave
the
grea
test
unc
erta
inty
and
requ
ire c
onsi
dera
ble
tim
e fo
r R&
D.
・R
emot
e m
aint
enan
ce a
nd
repa
ir te
chno
logi
es・E
xtra
ctio
n ch
rom
atog
raph
y eq
uipm
ent
・M
A re
cove
ry・C
entri
fuga
l ext
ract
or
・S
afeg
uard
tech
nolo
gy
・R
emot
e m
aint
enan
ce a
nd re
pair
tech
nolo
gies
・R
emot
e m
aint
enan
ce a
nd
repa
ir te
chno
logi
es
End
of t
he F
easi
bilit
y S
tudy
Pha
se II
10 y
ears
late
r
- 27 -
Adva
nced
aqu
eous
sys
tem
usi
ng th
e su
perc
ritic
al d
irect
ext
ract
ion
proc
ess
U-P
u-M
Apr
oduc
tsU
-Pu-
MA
prod
ucts
Hig
h-le
vel
radi
oact
ive
was
teU
pro
duct
sU
pro
duct
s
Cry
stal
lizat
ion
U
U/P
u/N
p
U/P
u/N
pA
m/C
m
Am/C
m/F
P
FPs
Sim
plifi
catio
n an
d co
mpa
ctifi
catio
nby
el
imin
atin
g th
e di
ssol
utio
n pr
oces
s
Sim
plifi
catio
n an
d co
mpa
ctifi
catio
nby
el
imin
atin
g th
e di
ssol
utio
n pr
oces
s
Dis
asse
mbl
ing
/ The
rmal
dec
ladd
ing
Spe
nt fu
elS
pent
fuel
Sup
ercr
itica
l dire
ct e
xtra
ctio
n pr
oces
s
Am
/Cm
re
cove
ry
Prin
cipl
e of
the
supe
rcrit
ical
dire
ct
extra
ctio
n pr
oces
s
Pow
dere
d sp
ent f
uel
U,P
u,N
p
TBP
-HN
O3
com
plex
-sup
ercr
itici
alC
O2
TBP
-HN
O3
com
plex
-sup
ercr
itici
al C
O2+
U,P
u,N
p Res
idue
mai
nly
cons
istin
g of
FP
s, e
tc.
From
pow
dere
d sp
ent f
uel,
With
out a
pply
ing
diss
olut
ion
proc
ess,
Into
sup
ercr
itica
l CO
2ga
sco
ntai
ning
TB
P-H
NO
3com
plex
,D
irect
ly e
xtra
ct U
-Pu-
Np.
⇒P
ossi
bilit
y of
impr
ovin
g ec
onom
y th
roug
h si
mpl
ified
pro
cess
Pre
sent
sta
tus
of th
e te
chno
logy
dev
elop
men
t
At a
sta
ge in
whi
ch th
e pr
inci
ple
is c
onfir
med
by
beak
er-
scal
e te
sts
usin
g sp
ent f
uel.
Alre
ady
com
mer
cial
ized
in g
ener
al in
dust
ries
in, f
or
exam
ple,
the
extra
ctio
n of
caf
fein
efro
m c
offe
e be
ans.
Ref
eren
ceFi
gure
3Su
perc
ritic
al d
irect
ext
ract
ion
proc
ess
