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Maekawa, Fujio
Ryoshi Bimu Kagaku No Kiso To Oyo; NSA/Commentaries, No.27, p.15 - 25, 2023/03
The nuclear transmutation technology that is one of the most beneficial industrial applications of quantum beams to humankind is explained.
Nuclear Science and Engineering Center; Fuel Cycle Design Office; Plutonium Fuel Development Center; Nuclear Plant Innovation Promotion Office; Fast Reactor Cycle System Research and Development Center; J-PARC Center
JAEA-Review 2022-052, 342 Pages, 2023/02
JAEA-Review-2022-052.pdf:18.05MB
This report summarizes the current status and future plans of research and development (R&D) on partitioning and transmutation technology in Japan Atomic Energy Agency, focusing on the results during the 3rd Medium- to Long-term Plan period (FY 2015-2021). Regarding the partitioning technology, R&D of the solvent extraction method and the extraction chromatography method are described, and regarding the minor actinide containing fuel technology, R&D of the oxide fuel production using the simplified pellet method, the nitride fuel production using the external gelation method, and pyrochemical reprocessing of the nitride fuel were summarized. Regarding transmutation technology, R&D of technology using fast reactors and accelerator drive systems were summarized. Finally, the new facilities necessary for the future R&D were mentioned.
Sasa, Toshinobu
Kasokuki, 18(4), p.233 - 240, 2022/01
Lead bismuth eutectic alloy (LBE) is a promising option as a spallation target for accelerator-driven transmutation systems (ADS) to reduce the radiological toxicity from long-lived radioactive waste. LBE is a heavy metal and has suitable characteristics both as a spallation target and as a coolant for transmutation systems. However, LBE is also known as a highly corrosive with structural materials. In this paper, technological developments to overcome the issue, the latest research activities such as hightemperature operation and oxygen concentration control to ensure corrosion resistance, are introduced together with the outline of the target for ADS.
Fukasawa, Yuto*; Kaneko, Masashi; Nakashima, Satoru*
Journal of Radioanalytical and Nuclear Chemistry, 329(1), p.77 - 84, 2021/07
Times Cited Count：1 Percentile：16.35(Chemistry, Analytical)Density functional theory calculations were applied to understand the selectivity between Am
and Eu ions with the crown ethers type ligands. 18C6 is predicted to form the most stable complex with Eu and show the higher stability for Am over Eu, being consistent with previously reported Am/Eu selectivity. We modeled N- and S-donor complexes by using framework of 18C6 complex and analyzed the complexation Gibbs energies, indicating that 18C6 with N-donor atoms is suitable for both complexation and higher Am stability over Eu due to the stronger covalent interaction.
Sasa, Toshinobu; Saito, Shigeru; Obayashi, Hironari; Ariyoshi, Gen
JPS Conference Proceedings (Internet), 33, p.011051_1 - 011051_6, 2021/03
To realize Accelerator-driven system (ADS) for minor actinide transmutation, JAEA proposes to construct the Proton Irradiation Facility in J-PARC. The facility is planned to solve technical issues for safe application of Lead-bismuth Eutectic Alloy (LBE). The 250 kW LBE spallation target will be located in the facility to prepare material irradiation database by both proton and neutron irradiation in the temperature range for typical LBE-cooled ADS. Various studies for important technologies required to build the facilities are investigated such as oxygen concentration control, instruments development, remote handling techniques for target maintenance, and spallation target design. The large scale LBE loops for mock up the 250 kW LBE spallation target and material corrosion studies are also manufactured and applied to various experiments. The latest status of 250 kW LBE spallation target design works will be summarized.
Morita, Yasuji; Nishihara, Kenji; Tsubata, Yasuhiro
JAEA-Data/Code 2018-017, 32 Pages, 2019/02
JAEA-Data-Code-2018-017.pdf:2.35MB
Potential radiotoxicity defined as a summation of intake dose was estimated for each actinide element to suppose target of recovery ratio of minor actinide (MA). Importance of each element from the viewpoint of the radiotoxicity was evaluated from the evolution of the radiotoxicity and ratio to the total radiotoxicity. In all the 4 types of spent fuels examined, Am is the most important element. For instance, the potential radiotoxicity of Am accounts for 93% of the total radiotoxicity of actinide elements in HLW produced by reprocessing of spent fuel from pressurized water reactor (PWR). Residual Pu after the recovery of 99.5% in reprocessing still gives contribution that cannot be ignored in radiotoxicity. When the burn-up of the UO
fuel in PWR increased, the potential radiotoxicity of actinide elements increased almost in proportion to the burn-up, but in case of MOX fuel in PWR and minor-actinide-recycled MOX fuel in fast reactor, the radiotoxicity of actinide elements increased further. Much consideration is required for the recovery of actinide elements in HLW from different types of fuel.
Minato, Kazuo; Tsujimoto, Kazufumi; Tanabe, Hiromi*; Fujimura, Koji*
Nihon Genshiryoku Gakkai-Shi ATOMO
, 59(8), p.475 - 479, 2017/08
no abstracts in English
Oigawa, Hiroyuki; Nishihara, Kenji; Minato, Kazuo; Kimura, Takaumi; Arai, Yasuo; Morita, Yasuji; Nakayama, Shinichi; Katakura, Junichi
JAERI-Review 2005-043, 193 Pages, 2005/09
JAERI-Review-2005-043.pdf:16.13MB
JAERI has been conducting research and development on partitioning and transmutation (P&T) technology for long-lived nuclides to develop the double-strata fuel cycle concept, in accordance with the Atomic Energy Commission's "Research and Development of Technologies for Partitioning and Transmutation of Long-lived Nuclides - Status and Evaluation Report" issued in 2000. The double-strata fuel cycle concept consists of four major processes: partitioning, fuel fabrication, transmutation, and fuel processing. The five-year achievement and future perspectives for the technology on these processes are presented in this report. It also provides an analytical study on impacts of introducing P&T technology on waste management, and on deployment of P&T for the future nuclear energy system.
Oigawa, Hiroyuki
Genshiryoku eye, 49(7), p.74 - 77, 2003/07
An International Symposium on Accelerator Driven Transmutation System (ADS) and Asia ADS Network Initiative was held on March 24 and 25, 2003 by JAERI, Kyoto University, Osaka University, Tokyo Institute of Technology, and KEK. In the symposium, representatives of Japan, USA, Europe, Korea, and China presented their current status and future perspectives of ADS development, and discussion was held about the future international collaboration, especially for activation of interactions among Asian countries, and the promotion of interdisciplinary synergy between nuclear physics and nuclear engineering.
Matsumura, Tatsuro
no journal, ,
no abstracts in English
Matsumura, Tatsuro; Suzuki, Hideya; Tsubata, Yasuhiro; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Sagawa, Hiroshi
no journal, ,
no abstracts in English
Matsumura, Tatsuro; Ban, Yasutoshi; Suzuki, Hideya; Tsubata, Yasuhiro; Hotoku, Shinobu; Tsutsui, Nao; Suzuki, Asuka
no journal, ,
The new reprocessing and minor actinide (MA) separation processes using innovative extractants in accord with CHON principle has been developed in Japan Atomic Energy Agency aimed for reduction of radioactive wastes from nuclear fuel cycle. The new nonorganophosphorus extractants which have appropriate extraction behaviors for each separation steps were developed. Continuous counter-current experiment of each solvent extraction process with uranium, plutonium and tracers of minor actinides were carried out. The experimental results showed that the separation performance of the solvent extraction processes were demonstrated successfully.
Tsujimoto, Kazufumi
no journal, ,
The Government of Japan periodically formulates the Basic Energy Plan in accordance with an article in the Basic Act on Energy Policy that entered into force in 2002. The latest version, called the Strategic Energy Plan, was issued in April, 2014. The largest change from the previous versions must be the accident of the Fukushima Daiichi Nuclear Power Plant. In spite of the accident, the Plan defines the nuclear power as an important base-load power source as a low carbon and quasi-domestic energy source, contributing to stability of energy supply-demand structure, on major premise of ensuring of its safety. The Plan puts emphasis on the importance of activities to resolve the challenge of how to manage and dispose of spent fuel, as well as the Fukushima restoration, safety operation of nuclear plants, and public acceptance. As for the P&T technology, the Government will promote technology development on volume reduction and mitigation of degree of harmfulness of radioactive waste. Specifically, development of technologies for decreasing the radiation dose remaining in radioactive waste over a long period of time and enhancing the safety of processing and disposal of radioactive waste, including nuclear transmutation technology using fast reactors and accelerators, will be promoted by utilizing global networks for cooperation. Based on this new Strategic Energy Plan, research and development (R&D) on P&T are being accelerated in Japan. The Japan Atomic Energy Agency (JAEA) has been continuously implementing R&D on P&T technology to reduce the burden of the backend of the nuclear fuel cycle. The R&D on P&T in JAEA are basing on two kinds of concepts: one is the homogeneous recycling of minor actinide (MA) in fast reactors and the other is the dedicated MA transmutation, so-called double-strata strategy, using an accelerator-driven system (ADS). In this work, recent R&D activities based on these policies are briefly shown.
Tsujimoto, Kazufumi
no journal, ,
To continue the utilization of the nuclear fission energy, the management of the high-level radioactive waste (HLW) is one of the most important issues to be solved. Partitioning and Transmutation (P&T) technology of HLW is expected to be effective to mitigate the burden of the HLW disposal by reducing the radiological toxicity and heat generation. The Japan Atomic Energy Agency (JAEA) has been conducting the research and development (R&D) on accelerator-driven subcritical system (ADS) as a dedicated system for the transmutation of long-lived radioactive nuclides. The ADS proposed by JAEA is a lead-bismuth eutectic (LBE) cooled fast subcritical reactor with thermal output of 800 MW. JAEA's reference design of ADS is a tank-type subcritical reactor, where lead-bismuth eutectic (LBE) is used as both the primary coolant and the spallation target. The central part of the core is the spallation target region. In the target region, LBE is flowing from the core bottom. The proton linac with the proton energy of 1.5 GeV is used for the accelerator to operate the ADS. A tank-type system is adopted to take advantage of a simple design and to eliminate the necessity of heavy primary piping. All primary components, including primary pumps, steam generators, and auxiliary heat exchangers, are accommodated within the reactor vessel. The primary cooling system includes two mechanical pumps and four steam generators. For the core fuel, (MA,Pu)-nitride is used. As inert matrix, zirconium-nitride (ZrN) is used with the fuel. Since the transmutation rate of MA is 250 kg/yr as described before, the relative transmutation efficiency of MA is about 10 %/yr. For ADS to play important roles in the nuclear fuel cycle, several critical issues have to be resolved. Items of R&D are divided into three technical areas peculiar to the ADS. For these technical areas, various R&D activities are progressing in JAEA.
Sugawara, Takanori
no journal, ,
Partitioning and transmutation (P&T) technology of long lived radioactive nuclides such as minor actinides (MAs) will be a promising technology to reduce the burden of the geological disposal of the high-level radioactive waste (HLW). The Japan Atomic Energy Agency (JAEA) has been continuously performing research and development (R&D) on the P&T technology. The R&D on the P&T technology in JAEA is based on two concepts: one is the homogeneous recycling of MA in fast breeder reactors (FBRs) and the other is the dedicated MA transmutation cycle, double-strata strategy, using an accelerator-driven system (ADS). In this presentation, the current status of the R&D for the ADS in JAEA will be introduced.
Araki, Yuta*; Morita, Misaki*; Fukutani, Satoshi*; Tsubata, Yasuhiro; Matsumura, Tatsuro; Fujii, Toshiyuki*
no journal, ,
no abstracts in English
Morita, Misaki*; Araki, Yuta*; Uehara, Akihiro*; Fukutani, Satoshi*; Tsubata, Yasuhiro; Matsumura, Tatsuro; Fujii, Toshiyuki*
no journal, ,
no abstracts in English
Suzuki, Akihiro*; Mizusako, Fumiki*; Inagaki, Yaohiro*; Arima, Tatsumi*; Fukasawa, Tetsuo*; Hoshino, Kuniyoshi*; Muroya, Yusa*; Matsumura, Tatsuro
no journal, ,
no abstracts in English
Tsujimoto, Kazufumi; Hayashi, Hirokazu; Matsumura, Tatsuro; Takano, Masahide
no journal, ,
To continue the utilization of the nuclear fission energy, the management of the high-level radioactive waste is one of the most important issues to be solved. Partitioning and Transmutation technology of HLW is expected to be effective to mitigate the burden of the HLW disposal by reducing the radiological toxicity and heat generation. The Japan Atomic Energy Agency (JAEA) has been conducting the research and development on accelerator-driven subcritical system (ADS) as a dedicated system for the transmutation of long-lived radioactive nuclides. This paper overviews the recent progress and future R&D plan of the study on the ADS and related fuel cycle technology in JAEA.
Matsumura, Tatsuro; Ban, Yasutoshi; Suzuki, Hideya; Tsubata, Yasuhiro; Hotoku, Shinobu; Tsutsui, Nao; Suzuki, Asuka; Toigawa, Tomohiro; Kurosawa, Tatsuya*; Shibata, Mitsunobu*; et al.
no journal, ,
To continue the utilization of the nuclear fission energy, the management of the high-level radioactive waste is one of the most important issues to be solved. Partitioning and Transmutation technology is expected to be effective to mitigate the burden of the HLW disposal by reducing the radiological toxicity and heat generation. JAEA has been conducting R&D on the MA separation process to remove of MA from HLW and supply the recovered MA to the transmutation system such as ADS. The MA separation process contains three steps. For An(III)+RE recovery process, we developed TDdDGA which has very high performance to recover of MA from high level waste. HONTA and ADAAM were developed for An(III)/RE separation process and Am/Cm separation process respectively. All extractants satisfy CHON principle to minimization of the secondary waste from the process. The separation performances of the flowsheets were evaluated by continuous extraction tests using simulated and genuine high level liquid waste.
