Refine your search:     
Report No.
 - 
Search Results: Records 1-7 displayed on this page of 7
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Promoting nuclear fuel cycle and ensuring nuclear non-proliferation/nuclear security

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.

JAEA Reports

Assessment report on research and development activities; Activity "Research and development on fast reactor cycle technologies" (Interim report)

Sector of Fast Reactor and Advanced Reactor Research and Development

JAEA-Evaluation 2019-004, 47 Pages, 2019/06

JAEA-Evaluation-2019-004.pdf:2.32MB
JAEA-Evaluation-2019-004-appendix(CD-ROM).zip:14.87MB

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.

JAEA Reports

Assessment report of research and development activities in FY2014; Activities "R&D plan on FR cycle technologies" (Pre-review report)

Sector of Fast Reactor Research and Development

JAEA-Evaluation 2015-006, 43 Pages, 2015/09

JAEA-Evaluation-2015-006.pdf:1.15MB
JAEA-Evaluation-2015-006-appendix(CD-ROM).zip:21.35MB

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.

JAEA Reports

Assessment report of research and development activities in FY2014; Activities "R&D programs on FBR/FR cycle technologies" and "R&D programs on prototype fast breeder reactor Monju and its related activities"(Post-review report)

Sector of Fast Reactor Research and Development

JAEA-Evaluation 2015-005, 77 Pages, 2015/09

JAEA-Evaluation-2015-005.pdf:1.9MB
JAEA-Evaluation-2015-005-appendix(CD-ROM).zip:54.13MB

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.

Oral presentation

Current status and issues on ODS tempered martensitic steel development for performance enhancement of advanced nuclear power system

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.

Oral presentation

Application of partitioning and transmutation technology to waste management; Assessment of total performance of advanced nuclear fuel cycle, 4; Assessment for fast reactor cycle

Watanabe, So; Sasa, Toshinobu; Owada, Hitoshi*; Saito, Takumi*; Ishio, Takahiro*; Murakami, Tsuyoshi*; Shimada, Takashi*

no journal, , 

no abstracts in English

Oral presentation

Advanced reactor research and development activities in JAEA

Hayafune, Hiroki

no journal, , 

no abstracts in English

7 (Records 1-7 displayed on this page)
  • 1