Refine your search:     
Report No.
 - 
Search Results: Records 1-12 displayed on this page of 12
  • 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

Results of the IAEA ARTEMIS review of JAEA's back-end strategy

Meguro, Yoshihiro

Kiho Enerugi Sogo Kogaku, 45(2), p.1 - 7, 2022/07

Japan Atomic Energy Agency (JAEA) has decided to terminate operation and decommission about half of its nuclear facilities during the third mid-to-long term period. In line with this decision, JAEA has been developing policies and plans for back-end measures such as decommissioning of these facilities and radioactive waste management, and has compiled and published the back-end roadmap and the medium- to-long term plan for the facilities, respectively. In April 2021, the back-end measures were reviewed by the IAEA's ARTEMIS review service, and eight international experts evaluated the back-end measures developed by JAEA and provided many useful recommendations and suggestions for the future promotion of the measures. In this paper, an overview of the ARTEMIS review, the results of the evaluation and the recommendations are be presented.

Journal Articles

Thermal-hydraulics technological strategy roadmap 2017; An Approach for continuous safety improvement of LWRs

Itoi, Tatsuya*; Iwaki, Chikako*; Onuki, Akira*; Kito, Kazuaki*; Nakamura, Hideo; Nishida, Akemi; Nishi, Yoshihisa*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 60(4), p.221 - 225, 2018/04

no abstracts in English

Journal Articles

Thermal-hydraulics technological strategy roadmap that improves safety of LWRs

Arai, Kenji*; Umezawa, Shigemitsu*; Oikawa, Hirohide*; Onuki, Akira*; Nakamura, Hideo; Nishi, Yoshihisa*; Fujii, Tadashi*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 58(3), p.161 - 166, 2016/03

no abstracts in English

Journal Articles

New AESJ thermal-hydraulics roadmap for LWR safety improvement and development after Fukushima accident

Nakamura, Hideo; Arai, Kenji*; Oikawa, Hirohide*; Fujii, Tadashi*; Umezawa, Shigemitsu*; Abe, Yutaka*; Sugimoto, Jun*; Koshizuka, Seiichi*; Yamaguchi, Akira*

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.5353 - 5366, 2015/08

Oral presentation

Thermal-hydraulics technological strategy roadmap for LWR safety improvement and development

Nakamura, Hideo; Arai, Kenji*; Oikawa, Hirohide*; Umezawa, Shigemitsu*; Onuki, Akira*; Fujii, Tadashi*; Nishi, Yoshihisa*; Abe, Yutaka*; Sugimoto, Jun*; Koshizuka, Seiichi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Technical issues for safety improvement, 5; Safety analysis

Nakamura, Hideo; Yamamoto, Yasushi*; Yamada, Hidetomo*; Nagayoshi, Takuji*; Nishi, Yoshihisa*

no journal, , 

no abstracts in English

Oral presentation

Technical issues for safety improvement, 1; Core damage prevention in case of accidents

Nishi, Yoshihisa*; Arai, Kenji*; Oikawa, Hirohide*; Fujii, Tadashi*; Umezawa, Shigemitsu*; Yamada, Hidetomo*; Nakamura, Hideo

no journal, , 

no abstracts in English

Oral presentation

Technical issues for safety improvement, 2; Validation of effectiveness of heat removal using SG secondary system in PWR

Onuki, Akira*; Umezawa, Shigemitsu*; Yamada, Hidetomo*; Nishi, Yoshihisa*; Arai, Kenji*; Oikawa, Hirohide*; Fujii, Tadashi*; Nakamura, Hideo

no journal, , 

no abstracts in English

Oral presentation

Technical issues for safety improvement, 3; Integrity of reactor pressure vessel

Fujii, Tadashi*; Arai, Kenji*; Oikawa, Hirohide*; Umezawa, Shigemitsu*; Nishi, Yoshihisa*; Nakamura, Hideo

no journal, , 

no abstracts in English

Oral presentation

Technical issues for safety improvement, 4; Integrity of containment

Oikawa, Hirohide*; Arai, Kenji*; Fujii, Tadashi*; Umezawa, Shigemitsu*; Nishi, Yoshihisa*; Nakamura, Hideo

no journal, , 

no abstracts in English

Oral presentation

Progress of research and development and design study on sodium-cooled fast reactor and strategy for the development in Japan

Kamide, Hideki

no journal, , 

Progress of Research and Development and design study on sodium cooled fast reactor in Japan is shown especially for safety. Further, activity to establish a Strategic Roadmap of the fast reactor development is introduced based on the Ministerial Meeting for the Nuclear Energy Policy held last year.

Oral presentation

AESJ new thermo-hydraulics roadmap for LWR safety improvement based on lessons-learned from Fukushima Daiichi accident

Nakamura, Hideo; Arai, Kenji*; Oikawa, Hirohide*; Fujii, Tadashi*; Umezawa, Shigemitsu*; Onuki, Akira*; Nishi, Yoshihisa*; Abe, Yutaka*; Sugimoto, Jun*; Koshizuka, Seiichi*; et al.

no journal, , 

12 (Records 1-12 displayed on this page)
  • 1