Development of level 2 PSA methodology for sodium-cooled fast reactors, 6; Development of technical basis in ex-vessel accident sequences

Ohno, Shuji ; Seino, Hiroshi ; Miyahara, Shinya

This research has compiled technical basis which is necessary to carry out a probabilistic safety assessment (Level 2 PSA) for a sodium-cooled fast reactor. The accumulated technical information consists of experimental and analytical information which help ones to understand the loading to a containment vessel, as well as the existing information on dominant factors of important ex-vessel phenomena.

Language	:	English
Journal	:	Proceedings of 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8) (CD-ROM)
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Pages	:	12 Pages
Publication Year/Month	:	2010/10
Meeting title	:	8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8)
Held date	:	2010/10
Location (city)	:	Shanghai
Location (country)	:	China
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Keywords	:	no keyword
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Registration No. : BB20101255
JAEA Abstracts No. : 39000106
Paper Submission No. : 8347

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