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Morita, Yasuji; Kimura, Takaumi
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), p.235 - 244, 2012/00
Separation process for transuranium elements (TRU = Am, Cm, Np and Pu) and some fission products (Sr, Cs and Mo) has been developed at Japan Atomic Energy Agency using new innovative extractants and adsorbents to improve the partitioning process from viewpoints of the economy and the reduction of secondary wastes. Phosphorus-free compounds consisting of carbon, hydrogen, oxygen and nitrogen (CHON principle) were applied to the separation steps for TRU, Cs and Sr by using solvent extraction or extraction chromatography. Mo is separated by adsorption with an iron oxide adsorbent. This paper gives results of the research and development of the separation process.
Sato, Takumi; Nishihara, Kenji; Hayashi, Hirokazu; Kurata, Masaki*; Arai, Yasuo
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), 9 Pages, 2012/00
Nitride fuel cycle for transmutation of long-lived minor actinides (MAs) has been developed in Japan Atomic Energy Agency (JAEA) under the double-strata nuclear fuel cycle concept. This study aims at developing the process flow diagram with the material balance sheet of the pyrochemical reprocessing of spent nitride fuel for ADS to evaluate the technological feasibility of the fuel cycle. Three process flow diagrams were proposed in this work: (1) the currently-proposed process with the molten salt electrorefining of spent nitride fuel, (2) the process with the molten salt electrorefining of the actinide-cadmium alloy after the chemical dissolution of spent nitride fuel, and, (3) the process combining the chemical dissolution of spent nitride fuel and the multi-stage counter current extraction. Moreover, the material balance was evaluated for the process (1) by use of the calculated and experimental data of the nitride fuel for ADS.
Matsumura, Tatsuro; Morita, Yasuji; Matsumura, Kazumi; Sano, Yuichi; Koma, Yoshikazu; Nomura, Kazunori
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), 8 Pages, 2012/00
no abstracts in English
Minato, Kazuo; Morita, Yasuji; Tsujimoto, Kazufumi; Koyama, Shinichi; Kurata, Masaki*; Inoue, Tadashi*; Ikeda, Kazumi*
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), p.341 - 349, 2012/00
In order to provide a quantitative assessment for the maturity of the partitioning and transmutation technology relative to its full-scale deployment, a technology readiness level (TRL) process was used. The definitions of TRL used in this study were based on those used in the Global Nuclear Energy Partnership (GNEP). The TRL was evaluated and the technology pathway was discussed for the systems of FBR and ADS for the minor actinides (MA) transmutation, MA partitioning processes, and MA-bearing fuels. Through the evaluation, it was recognized that hard requirements to be satisfied were present at TRL 5 for each technology development. The introduction of lab-scale tests with actual spent fuel for MA partitioning process and with actual separated materials for MA-bearing fuels fabrication and irradiation before the engineering scale tests may be effective and efficient solution.
Nishihara, Kenji; Sugawara, Takanori; Iwamoto, Hiroki; Alvarez Velarde, F.*; Rineiski, A.*
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), p.315 - 327, 2012/00
Accuracy of nuclear data, especially for minor actinides (MAs), is important in neutronics design of advanced reactors for MA transmutation such as an Accelerator-Driven System (ADS). Authors introduce the results of a benchmark activity in the IAEA CRP that revealed a discrepancy among k-effectives by different nuclear data libraries is as large as 3% even for an initial criticality before burn-up. In order to reduce this uncertainty, Transmutation Physics Experimental Facility (TEF-P) with a significant amount of MA is being proposed in the J-PARC project. An expected reduction of the uncertainty of criticality, void reactivity and Doppler coefficient by the TEF-P was numerically evaluated using the cross-section adjustment procedure based on the JENDL3.3. The uncertainty would be reduced from 1.3% to 0.6% if experimental results of the TEF-P and other past critical experiments were utilized to adjust nuclear data.
Tomiyama, Shin*; Mimura, Hitoshi*; Niibori, Yuichi*; Yamagishi, Isao; Morita, Yasuji
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), 10 Pages, 2012/00
The immobilization of Cs has been studied by the calcination of the Cs-form of various kinds of mordenites. In this study, the effect of various parameters such as calcining temperature and time, components in mordenites, conditions for cold and hot pressing, on the immobilization of Cs in ceramic products are evaluated by using X-ray diffractometry (XRD), density balance (Archimedes' method), scanning electron microscopy (SEM) and electron probe microanalysis (EPMA). Results showed that recrystallization to the stable ceramic solid forms of CsAlSi
O
was achieved only in calcination of Synthetic Mordenite-C which contains Ti and Fe as binder. The Cs-form mordenites were pelletized into a disk by cold isostatic pressing and the density of the solid forms increased with calcining temperature and time.
Oigawa, Hiroyuki; Minato, Kazuo; Morita, Yasuji; Kimura, Takaumi; Arai, Yasuo; Tsujimoto, Kazufumi; Nishihara, Kenji
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), p.123 - 132, 2010/11
After the first check and review on the partitioning and transmutation (PT) technology by the Japan Atomic Energy Commission (JAEC) in 2000, significant progress was made in respective research areas of the partitioning, fuel fabrication, transmutation and fuel recycling in Japan. The second check and review on the PT technology was made by the JAEC in 2008-2009. The final report issued in April, 2009, mentions that the significance of the PT technology is in three points: reduction of the potential hazard, mitigation of the requirement for geological repository site, and enhancement of the options in the design of the whole system of waste disposal. The current technology levels of the PT for both FBR and ADS were evaluated. The PT technology in general is still in the basic research because of the lack of experimental data for minor actinides (MA). It was, therefore, strongly recommended to accumulate the experimental data for MA as a common basis for both FBR and ADS.
Koma, Yoshikazu; Sano, Yuichi; Nomura, Kazunori; Watanabe, So; Matsumura, Tatsuro; Morita, Yasuji
no journal, ,
Engineering system of the extraction chromatography for Am and Cm separation from spent FBR fuel is under development. Concerning the process development, experimental data including separation, safety and treatment after use was collected and evaluated that the combination of TODGA and R-BTP adsorbent was the most promising at present. Concerning the column system development, preparing a stationary phase bed, hydraulics of mobile phase, temperature control, discharging hydrogen which is radiolytically generated, column plugging which will bring a safety concern were investigated and it was revealed that the system has a potential for engineering application.
