Refine your search:     
Report No.
 - 
Search Results: Records 1-10 displayed on this page of 10
  • 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

Consideration of creep relaxation initial stress setting method used to inelastic analysis for fast reactor components design

Noi, Hiromi*; Watanabe, Sota*; Kubo, Koji*; Okajima, Satoshi; Ando, Masanori

Nihon Kikai Gakkai M&M 2023 Zairyo Rikigaku Kanfarensu Koen Rombunshu (Internet), p.CL0712_1 - CL0712_5, 2023/09

no abstracts in English

Journal Articles

Progress in conceptual design of a pool-type sodium-cooled fast reactor in Japan

Kato, Atsushi; Kubo, Shigenobu; Chikazawa, Yoshitaka; Miyagawa, Takayuki*; Uchita, Masato*; Suzuno, Tetsuji*; Endo, Junji*; Kubo, Koji*; Murakami, Hisatomo*; Uzawa, Masayuki*; et al.

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet), 11 Pages, 2022/04

The authors are carrying out conceptual design studies for a pool-type sodium-cooled fast reactor. There are main challenges such as measures against severe earthquake in Japan, thermal hydraulic in a reactor vessel (RV), a decay heat removal system design. When the JP-pool SFR of 650 MWe is installed in Japan, it shall be designed against the severe seismic conditions. Additionally, a newly three-dimensional seismic isolation system is under development.

Journal Articles

Study of the calculation method for the elastic follow-up coefficient by inelastic analysis

Watanabe, Sota*; Kubo, Koji*; Okajima, Satoshi; Wakai, Takashi

Nihon Kikai Gakkai M&M 2017 Zairyo Rikigaku Kanfarensu Koen Rombunshu (Internet), p.581 - 585, 2017/10

no abstracts in English

Journal Articles

Study on the seismic buckling evaluation method for Mod. 9Cr-1Mo steel cylindrical vessel

Okafuji, Takashi*; Miura, Kazuhiro*; Sago, Hiromi*; Murakami, Hisatomo*; Kubo, Koji*; Sato, Kenichiro*; Wakai, Takashi; Shimomura, Kenta

Nihon Kikai Gakkai M&M 2017 Zairyo Rikigaku Kanfarensu Koen Rombunshu (Internet), p.591 - 595, 2017/10

no abstracts in English

Oral presentation

Creep strength of modified 9Cr-1Mo steel repair welding

Yamashita, Hayato; Yamashita, Takuya; Onizawa, Takashi; Nagae, Yuji; Yamamoto, Kenji*; Shudo, Shingo*; Kawasaki, Kenji*; Kubo, Koji*

no journal, , 

no abstracts in English

Oral presentation

Thermal transient evaluation of pool-type SFR

Kato, Atsushi; Onoda, Yuichi; Miyagawa, Takayuki*; Endo, Junji*; Kubo, Koji*

no journal, , 

JAEA is studying 600 MWe pool-type sodium-cooled fast reactor. This report presents thermal hydraulic study in a reactor vessel and structural intactness evaluation in case of station black out and reactor trip.

Oral presentation

Investigation on daily load following operation in sodium cooled fast reactor

Aizawa, Kosuke; Chikazawa, Yoshitaka; Morohoshi, Kyoichi*; Kubo, Koji*; Uchita, Masato*

no journal, , 

no abstracts in English

Oral presentation

Study on characteristics of the elastic follow-up coefficient for the 3 kinds of inelastic behaviors

Noi, Hiromi*; Watanabe, Sota*; Kubo, Koji*; Okajima, Satoshi; Ando, Masanori

no journal, , 

no abstracts in English

Oral presentation

Creep-fatigue life evaluation considering metallurgical discontinuity and stress redistribution in 316FR steel welded joint test pieces

Oshikiri, Masato*; Kubo, Koji*; Ando, Masanori; Yamashita, Hayato

no journal, , 

no abstracts in English

Oral presentation

Creep-fatigue life evaluation considering metallurgical discontinuity and stress redistribution in Mod. 9Cr-1Mo steel welded joint test pieces

Oshikiri, Masato*; Kubo, Koji*; Ando, Masanori; Yamashita, Hayato

no journal, , 

no abstracts in English

10 (Records 1-10 displayed on this page)
  • 1