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Tasaki, Yudai
Kaku Nenryo, (56), P. 5, 2021/05
no abstracts in English
Kakiuchi, Kazuo
Kaku Nenryo, (55-1), p.25 - 30, 2019/12
This report describes the outline of the 31st summer seminar of the Nuclear Fuel Division of the Atomic Energy Society of Japan, which was held in Matsushima, Miyagi, from July 10 to 12, 2019.
Kakiuchi, Kazuo
Kaku Nenryo, (55-1), p.21 - 24, 2019/12
Japan Atomic Energy Agency (JAEA) holds the international meeting, "Fuel Safety Research Meeting" (FSRM). The purpose of this meeting is to exchange information and make discussion with domestic and foreign experts in terms of the safety of light-water reactor fuel. This report describes the outline of FSRM2019 held in Mito, Ibaraki, on October 28 and 29, 2019.
Narukawa, Takafumi
Kaku Nenryo, (54-2), P. 3, 2019/07
no abstracts in English
Taniguchi, Yoshinori; Kakiuchi, Kazuo; Amaya, Masaki
Kaku Nenryo, (54-1), p.16 - 19, 2019/03
Japan Atomic Energy Agency (JAEA) holds the international meeting, "Fuel Safety Research Meeting" (FSRM). The purpose of this meeting is to exchange information and make discussion with domestic and foreign experts in terms of the safety of light-water reactor fuel. This report describes the outline of FSRM2018 held in Mito, Ibaraki, on October 30 and 31, 2018.
Takano, Masahide
Wagakuni Shorai Sedai No Enerugi O Ninau Kakunenryo Saikuru; Datsu Tanso Shakai No Enerugi Anzen Hosho; NSA/Commentaries, No.24, p.163 - 167, 2019/03
This article summarizes R&D status of the nitride fuel cycle for minor actinides (MA) transmutation. Status of nitride fuel fabrication, material properties and fuel performance code, pyrochemical reprocessing, and nitrogen-15 enrichment are described.
Morishita, Yoshitsugu; Yanagisawa, Tsutomu*
Wagakuni Shorai Sedai No Enerugi O Ninau Kakunenryo Saikuru; Datsu Tanso Shakai No Enerugi Anzen Hosho; NSA/Commentaries, No.24, p.119 - 126, 2019/03
no abstracts in English
Narukawa, Takafumi
Kaku Nenryo, (53-2), P. 5, 2018/08
no abstracts in English
Miwa, Shuhei
Kaku Nenryo, (50-2), p.19 - 20, 2015/06
I worked in CEA Cadarache of France as a secondee for 1 year from October, 2014. I could have a fulfilling research life and build up a network of personal contacts with specialist in foreign research institutes through the research collaboration with CEA about fission product release behavior from degraded fuel under a severe accident.
Tamaki, Hitoshi
Tekisuto "Kakunenryo Saikuru" (Internet), 3 Pages, 2014/12
Revised regulatory rule of nuclear facilities in Japan defines "Serious accident", and require accident measures for them to not only power reactors, but also fuel reprocessing and fabrication facilities. This document describes the basis of accident measures for Serious accident at nuclear fuel reprocessing and fabrication facilities, as a part of "Text of Nuclear Fuel Cycle".
Hatanaka, Koichiro; Shibata, Masahiro
Tekisuto "Kakunenryo Saikuru" (Internet), 6 Pages, 2014/06
no abstracts in English
Takeuchi, Kentaro
Tekisuto "Kakunenryo Saikuru" (Internet), 4 Pages, 2013/02
no abstracts in English
Minato, Kazuo
Kaku Nenryo, (48-1), p.27 - 30, 2012/12
Japan Atomic Energy Agency set up Fukushima Project Teams at Nuclear Science Research Institute, Nuclear Fuel Cycle Engineering Laboratories, and Oarai Research and Development Center to conduct research and development towards decommissioning of Fukushima Daiichi Nuclear Power Plants on the 1st of April, 2012. Fukushima Project Team at Nuclear Science Research Institute is involved in specific research and development projects concerning the spent fuel pool countermeasures, preparation of fuel debris removal, and radioactive waste treatment and disposal. Among these specific research and development projects the accident development analysis and the assessment of simulated fuel debris characteristics are related to nuclear fuel materials research.
Amamoto, Ippei
Tekisuto "Kakunenryo Saikuru" (Internet), 10 Pages, 2012/12
no abstracts in English
Katsuyama, Kozo
Kaku Nenryo, (43-1), p.7 - 13, 2007/10
no abstracts in English
Umeda, Miki
Nihon Genshiryoku Gakkai Kaku Nenryo Bukai Homu Peji (Internet), 2 Pages, 2007/06
no abstracts in English
Sato, Isamu
Kaku Nenryo, (42-2), p.42_2_13 - 42_2_16, 2007/02
In the safety research for severe accidents of atomic power plants, it's of value to evaluate kinds and amounts of radioactive species released into the environment during atomic reactor accidents, which is called "source term". Especially, there are no experimental source term data for irradiated fast reactor fuels under the temperature over the melting point of fuels. JAEA has performed some experimental researches of FP release behavior in order to recognize the source term in FR plants with mixed oxide fuels irradiated in the experimental fast reactor, "JOYO". In the tests for oxide fuels, the time-dependence of the release rate of Cs indicate that Cs release could controlled not only by diffusion in fuel but also by vaporization. The source term results for nitride fuel were partly differed from those for oxide fuel. With thermochemical consideration, we indicated that the oxygen partial pressure around oxide fuel under the test was higher than around nitride fuel.
Sato, Isamu
Nihon Genshiryoku Gakkai Kaku Nenryo Bukai Dai-21-kai "Kaku Nenryo, Kaki Semina" Kogi Tekisuto, 20 Pages, 2006/07
In the sphere of safety research of atomic power plants, it's of value to evaluate "source term" of radioactive species released into the environment during atomic reactor accidents. The high level accuracy is needed for the source term in points of safety and economic views. Especially, there are no experimental source term data for irradiated FR fuels under the temperature over the melting point of fuels and at rapid heating rate. Therefore, the experimental data for LWR fuels have been applied for the source term evaluation of FRs with some conservative assumptions. FP behavior in irradiated mixed nitride fuel with high FP gas entrapment function and high thermal conductivity and the material properties have been studied with the equivalent heating tests and a molecular orbital method, respectively. These results contributed to the source term evaluation and the swelling behavior related to the scenario during re-criticality of FRs.
Nakazono, Yoshihisa
Kaku Nenryo, (41-2), p.41_2_60 - 41_2_61, 2006/01
no abstracts in English
Sawa, Kazuhiro
Nihon Genshiryoku Gakkai Kaku Nenryo Bukai Dai-20-kai "Kaku Nenryo, Kaki Semina" Kogi Tekisuto, 18 Pages, 2005/07
JAERI has proceeded research and development (R&D) of High Temperature Gas-cooled Reactor (HTGR) fuels under HTTR project. This paper reports major R&D results and future R&D programs.
