Koyama, Shinichi; Mitsugashira, Toshiaki
Proceedings of 9th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, p.509 - 518, 2007/00
In order to evaluate the transmutation behavior of americium under fast and thermal neutron spectra, two kinds of irradiated Am oxide samples were analyzed by radiochemical methods in Japan Atomic Energy Agency. One is Am encapsulated in a vanadium capsule which was irradiated in the experimental fast reactor JOYO for 275 effective full power days (EFPD) under the fast neutron flux of 310 c/cms. The other is Am oxide pelletized with MgO which was irradiated in Japan Material Testing Reactor for 207 EFPD under the thermal neutron flux of 210 c/cms. After dissolution of these samples, americium, curium and plutonium were chemically separated and their isotope compositions were analyzed by alpha and -ray spectrometry and mass spectroscopy. Cs and Nd were measured by -ray spectrometry and mass spectroscopy, respectively, to determine the total fission events and burnup. Am, Am, Pu and Cm were clearly observed. The total transmutation ratios of americium under the fast and thermal neutron spectra were about 10% and 80% in the irradiation conditions, respectively. The fission to capture cross-section ratios were evaluated in order to compare the transmutation behavior of americium. As the result, it is proved that the accumulation of even-even nuclei, such as Cm and Cm, in the thermal neutron spectrum was remarkable than that under the fast neutron spectrum. It is expected that these results show the important aspect to discuss the transmutation concept by using several neutron reaction in the reactor. In this study, the fundamental analytical data could be obtained.
Oigawa, Hiroyuki; Nishihara, Kenji; Tsujimoto, Kazufumi; Takei, Hayanori; Kikuchi, Kenji; Kurata, Yuji; Saito, Shigeru; Mizumoto, Motoharu; Sasa, Toshinobu; Sugawara, Takanori; et al.
Proceedings of 9th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, p.371 - 382, 2007/00
JAEA has been conducting the R&D on accelerator-driven subcritical system (ADS) as a dedicated system for the transmutation of long-lived radioactive nuclides. The ADS can co-exist with FBR symbiotically and complementarily to enhance the reliability and the safety of the commercial FBR cycle. The R&D activities in JAEA include neutronics, thermal-hydraulic and structural design, transient analysis in case of beam trips, development of spallation target using Pb-Bi, research on the materials, and cost estimation. In addition, the high-intensity proton accelerator project J-PARC is under construction. One of the main experimental facilities of the J-PARC is the Transmutation Experimental Facility (TEF), which is assigned as Phase-II of the project.
Ozawa, Masaki; Fujita, Reiko*; Koyama, Shinichi; Suzuki, Tatsuya*; Fujii, Yasuhiko*
Proceedings of 9th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, p.315 - 324, 2007/00
Catalytic Electrolytic extraction method has been studied as a separation tool for rare metal fission products, RMFP in the spent nuclear fuel. In an employed CEE process, Pd cation itself would not only be easily deposited from various nitric acid solutions, but enhance also the deposition of co-existing RuNO, ReO and TcO by acting as a catalyst. The quaternary-, Pd-Ru-Rh-Re, deposit Pt or Ti electrode, fabricated by CEE, suggested the highest cathodic current corresponding to the hydrogen generation reaction in both alkaline solution and sea water. Advanced ORIENT Cycle, where ion exchange chromatography using tertiary pyridine resin and the CEE employ as mainstay separation technology, will enhance separation and utilization of actinide and fission product, and thus be expected to realize ultimate reducing radioactive wastes.
Kimura, Takaumi; Komaki, Jun; Morita, Yasuji
Proceedings of 9th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, p.151 - 158, 2007/00
The Japan Atomic Energy Agency (JAEA) has been conducting research and development (R&D) on partitioning and transmutation (P&T) technologies using commercialized fast reactors (FR) or accelerator driven system (ADS) in the transmutation cycle. Various partitioning technologies have been investigated in the R&D activities for aqueouspartitioning of radioactive nuclides, especially actinides. This paper overviews some of the activities on the partitioning at JAEA.
Arai, Yasuo; Akabori, Mitsuo; Minato, Kazuo
Proceedings of 9th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, p.117 - 126, 2007/00
JAEA's R&D activities on nitride fuel research for transmutation of long-lived minor actinide (MA) are described. Nitride fuel containing MA as a principal component is proposed as a fuel material in sub-critical core of the Accelerator Driven System (ADS) developed by JAEA. Among the recent results, those on preparation of MA-bearing nitrides, property measurements of MA-bearing nitrides and burn-up simulated nitrides, pyrochemical treatment of spent nitride fuel and irradiation behavior of U-free nitride fuel are introduced.
Minato, Kazuo; Ichimiya, Masakazu; Inoue, Tadashi*
Proceedings of 9th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, p.35 - 43, 2007/00
no abstracts in English