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Journal Articles

Event tree analysis for material relocation on core catcher in a sodium-cooled fast reactor

Yamano, Hidemasa; Kubo, Shigenobu; Kan, Taro*; Shibata, Akihiro*; Hourcade, E.*; Dirat, J. F.*

Proceedings of 29th International Conference on Nuclear Engineering (ICONE 29) (Internet), 10 Pages, 2022/08

In this paper, the approach to event tree development and the scope of the event tree analysis were described with key points on core catcher loading. For the analytical conditions, two core catcher loading conditions were given as bounding and conservative cases. For important heading of the event tree, key important phenomena were included: strong back design, fuel-coolant interaction and quench in the sodium plenum design, jet attack, criticality and coolability on the core catcher. In this paper, preliminary trial quantification was attempted using a probability ranking table which is based on engineering judgement. This event tree analysis has identified the dominant sequence, and clarified the effect of the core catcher loading and effectiveness of design measures. This study suggests that the criticality measure is very important for the core catcher study.

Journal Articles

Model verification and validation procedure for a neutronics design methodology of next generation fast reactors

Ohgama, Kazuya; Ikeda, Kazumi*; Ishikawa, Makoto; Kan, Taro*; Maruyama, Shuhei; Yokoyama, Kenji; Sugino, Kazuteru; Nagaya, Yasunobu; Oki, Shigeo

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 10 Pages, 2017/04

Journal Articles

Core performance requirements and design conditions for next-generation sodium-cooled fast reactor in Japan

Oki, Shigeo; Maruyama, Shuhei; Chikazawa, Yoshitaka; Ohtaki, Akira; Kubo, Shigenobu; Hibi, Koki*; Kan, Taro*

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 9 Pages, 2017/04

Journal Articles

Core design of the next-generation sodium-cooled fast reactor in Japan

Kan, Taro*; Ogura, Masashi*; Hibi, Koki*; Oki, Shigeo; Maeda, Seiichiro; Maruyama, Shuhei; Ohgama, Kazuya

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 10 Pages, 2017/04

Oral presentation

Self-regeneration of perovskite-based catalyst, 1; Crystal structure

Taniguchi, Masashi*; Kan, C. Y.*; Uenishi, Mari*; Tanaka, Hirohisa*; Matsumura, Daiju; Nishihata, Yasuo; Mizuki, Junichiro; Uozumi, Akifumi*; Hamada, Ikutaro*; Morikawa, Yoshitada*

no journal, , 

no abstracts in English

Oral presentation

Core neutronics design method for next generation FBRs, 4; Plan for development of core neutronics design method

Moriwaki, Hiroyuki*; Hibi, Koki*; Kan, Taro*; Oki, Shigeo; Kugo, Teruhiko; Okubo, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Development of core seismic assessment method toward the FBR

Murakami, Hisatomo; Kitamura, Seiji; Yamazawa, Tomoyuki*; Ikarimoto, Iwao*; Kan, Taro*

no journal, , 

no abstracts in English

Oral presentation

Consideration of directional effects of inner-ducts in fuel sub-assemblies to power distribution in JSFR core design

Moriwaki, Hiroyuki*; Kan, Taro*; Oki, Shigeo

no journal, , 

no abstracts in English

Oral presentation

Studies on the safety design guidelines of Generation-IV Sodium-cooled Fast Reactors, 7; Focal points of safety design guideline for reactor core

Tani, Akihiro*; Kan, Taro*; Okano, Yasushi

no journal, , 

Focal points on reactor core systems of the Safety Design Guidelines are presented based on next generation SFR designs, specifically on "Fuel", "Reactor core cooling ability", "Active shutdown system", "Reactor shutdown utilizing passive system or inherent feedbacks", "Recriticality-free and in-vessel retention approaches".

Oral presentation

Model V&V and UQ procedure for the neutronics design methodology for the next generation fast reactor, 1; Outline of model V&V and UQ procedure

Ohgama, Kazuya; Ikeda, Kazumi*; Ishikawa, Makoto; Kan, Taro*; Oki, Shigeo

no journal, , 

no abstracts in English

Oral presentation

Model V&V and UQ procedure for the neutronics design methodology for the next generation fast reactor, 2; Verification

Ikeda, Kazumi*; Kan, Taro*; Maruyama, Shuhei; Ohgama, Kazuya

no journal, , 

no abstracts in English

Oral presentation

Core design for the next generation sodium-cooled fast reactor, 1; Core performance requirements and design conditions

Oki, Shigeo; Chikazawa, Yoshitaka; Kubo, Shigenobu; Hibi, Koki*; Kan, Taro*

no journal, , 

no abstracts in English

Oral presentation

Core design for the next generation sodium-cooled fast reactor, 3; Design optimization for the core arrangement

Moriwaki, Hiroyuki*; Ogura, Masashi*; Kan, Taro*; Oki, Shigeo

no journal, , 

no abstracts in English

Oral presentation

Design of a low sodium void reactivity core concept of tank-type sodium-cooled fast reactor

Hasegawa, Takashi*; Kan, Taro*; Moriwaki, Hiroyuki*; Tokizaki, Minako*; Yamano, Hidemasa; Takano, Kazuya

no journal, , 

no abstracts in English

15 (Records 1-15 displayed on this page)
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