Published 1993 | Version v1
Book

Design review of SPWR with PSA methodology

  • 1. Japan Atomic Energy Research Inst., Ibaraki (Japan). Advanced LWR Technology Development Program Team
  • 2. Computer Software Development Co., Ltd., Minatoku (Japan). Scientific Engineering Dept.

Description

This paper presents the procedures and results of a PSA (Probabilistic Safety Assessment) of the SPWR (System-Integrated PWR), which is being developed at the Japan Atomic Energy Research Institute (JAERI) as a medium sized innovative passive safe reactor, to assist in the design improvement of the SPWR by reviewing the design and identifying the design weaknesses. This PSA was performed in four steps: (1) identification of initiating events by the failure mode effect analysis and other methods, (2) delineation of accident sequences for three selected initiating events using accident progression flow charts and event trees, (3) quantification of event trees based on the review of past PSAs for LWRs, and (4) sensitivity analysis and interpretation of results. Qualitative and quantitative results of PSA provided very useful information for decision makings of design improvement and recommendations for further consideration in the process of detailed design

Part of:
2nd ASME-JSME international conference on nuclear engineering -- 1993

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers (ASME).
Imprint Place
New York, NY (United States)
ISBN
0-7918-0637-5
Imprint Title
2nd ASME-JSME international conference on nuclear engineering -- 1993
Imprint Pagination
914 p.
Journal Page Range
p. 357-364.

Conference

Title
2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering.
Dates
21-24 Mar 1993.
Place
San Francisco, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
25058828
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
DESIGN; ENGINEERED SAFETY SYSTEMS; FAILURE MODE ANALYSIS; PWR TYPE REACTORS; REACTOR ACCIDENTS; SAFETY ANALYSIS; THEORETICAL DATA
Descriptors DEC
ACCIDENTS; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-930352--.