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Tamai, Hiroshi; Mochiji, Toshiro; Senzaki, Masao*; Iwamoto, Tomonori*; Ishiguro, Yuzuru*; Kitade, Yuta; Sato, Heigo*; Suehiro, Rie*; Taniguchi, Tomihiro*; Fukasawa, Tetsuo*; et al.
Dai-41-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2020/11
In light of recent delay of plutonium use in Japan and the increasing criticism of nuclear non-proliferation and nuclear security in the nuclear fuel cycle, the validity of these criticisms will be examined for the sustainable development of the nuclear fuel cycle policy. Issues on the view point of nuclear non-proliferation and nuclear security are examined.
Sector of Fast Reactor and Advanced Reactor Research and Development
JAEA-Evaluation 2019-004, 47 Pages, 2019/06
Japan Atomic Energy Agency (hereafter referred to as "JAEA") consulted with the "Evaluation Committee of Research and Development Activities for Fast Reactor Cycle" (hereinafter referred to as "Committee"), which consists of specialists in the fields of the evaluation subjects of fast reactor cycle technologies, for interim assessment of R&D activities of fast reactor cycle in the 3rd Mid- and Long-Term Plan (from April 2015 to March 2022) in accordance with "General Guideline for the Evaluation of Government Research and Development (R&D) Activities" by Cabinet Office, Government of Japan, "Guideline for Evaluation of R&D in Ministry of Education, Culture, Sports, Science and Technology" and Regulation on Conduct for Evaluation of R&D Activities" by JAEA. In response to the JAEA's request, the Committee assessed the R&D program of fast reactor cycle technologies during the period of four years from April 2015 to March 2018. The Committee evaluated the management and R&D activities based on the explanatory documents and oral presentations by JAEA. The results of the evaluation were compiled in assessment report that was organized including the reasons for evaluation and the opinions and recommendations. This report is issued for the purpose of actively disseminate evaluation information to the people of Japan (based on General Guideline), which lists the members of the Committee and outlines the assessment items and the review process for procedure of the assessment. The assessment report which was issued by the Committee is attached.
Sector of Fast Reactor Research and Development
JAEA-Evaluation 2015-006, 43 Pages, 2015/09
Japan Atomic Energy Agency (JAEA) asked the advisory committee "Evaluation Committee of Research and Development Activities for Fast Reactor Cycle" (the Committee) to assess "The Third Basic Plan on FR/FR Cycle technologies during the period between FY2015 and FY2021", in accordance with "General Guideline for the Evaluation of Government R&D Activities" by Japanese Cabinet Office, "Guideline Evaluation of R&D in Ministry of Education, Culture, Sports, Science and Technology" and "Regulation on Conduct for Evaluation R&D Activities" by JAEA. This report summarizes the result of proposal by the Committee.
Sector of Fast Reactor Research and Development
JAEA-Evaluation 2015-005, 77 Pages, 2015/09
Japan Atomic Energy Agency (JAEA) asked the advisory committee "Evaluation Committee of Research and Development Activities for Fast Reactor Cycle" (the Committee) to assess "R&D Programs on FBR/FR Cycle Technologies" and "R&D Programs on Prototype Fast Breeder Reactor Monju and its Related Activities" during the period between FY2010 and FY2014, in accordance with "General Guideline for the Evaluation of Government R&D Activities" by Japanese Cabinet Office, "Guideline Evaluation of R&D in Ministry of Education, Culture, Sports, Science and Technology" and "Regulation on Conduct for Evaluation R&D Activities" by JAEA. This report summarizes results of proposal by the Committee.
Otsuka, Satoshi; Tanno, Takashi; Yano, Yasuhide; Fujita, Koji; Shizukawa, Yuta; Hashidate, Ryuta; Onizawa, Takashi; Kaito, Takeji; Ito, Chikara
no journal, ,
Implementation of fusion energy system and fast reactor cycle system requires the development of advanced materials resistant to the severe core environment where high-temperature and high-dose neutron irradiation are superposed. A lot of efforts have been made worldwide for research and development of oxide dispersion strengthened (ODS) steels with a variety of specification; Japan Atomic Energy Agency (JAEA) has focused on the development of 9Cr,11Cr-ODS tempered martensitic steel (TMS) for high-burnup fuel cladding tube of sodium-cooled fast reactor (SFR). This paper overviews the current status on 9Cr,11Cr-ODS TMS cladding tube development in JAEA, and discusses the cross-cutting issues in material development for advanced nuclear power systems.
Watanabe, So; Sasa, Toshinobu; Owada, Hitoshi*; Saito, Takumi*; Ishio, Takahiro*; Murakami, Tsuyoshi*; Shimada, Takashi*
no journal, ,
no abstracts in English
Hayafune, Hiroki
no journal, ,
no abstracts in English