Probabilistic risk assessment method development for high temperature gas-cooled reactors, 1; Review of requirements on scenario identification and reliability data development

Muramatsu, Ken*; Muta, Hitoshi*; Matsuda, Kosuke*; Sato, Hiroyuki ; Nishida, Akemi ; Ohashi, Hirofumi ; Itoi, Tatsuya*; Tanabe, Masayuki*

As part of PRA method development for High temperature Gas-cooled Reactor, domestic and international PRA standards are investigated to identify requirements related to accident scenario assessment and reliability database development. It was concluded that there are three key thing to note for the PRA method development, that is, detail analysis for passive components, integration of mechanistic source term evaluation and supplementation of reliability data.

Language	:	Japanese
Journal	:
Volume	:
Number	:
Pages	:
Publication Year/Month	:
Meeting title	:	日本原子力学会2016年秋の大会
Held date	:	2016/09
Location (city)	:	久留米
Location (country)	:	日本
Patent information	:
PDF	:
Paper URL	:
DOI for research data	:
Keywords	:	高温ガス炉; 確率論的リスク評価
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:

Accesses	:	- Accesses
Web of Science® Times Cited Count	:	Times Cited Count： If you would like to get the latest times cited, please access the Web of Science®. http://www.webofknowledge.com/wos
InCites™	:
Altmetrics	:

Registration No. : BB20160602
JAEA Abstracts No. :
Paper Submission No. :

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.