Published 1989 | Version v1
Journal article Metadata-only

Recent trends in PRA [probabilistic risk assessment] results for large early releases from PWR [pressurized water reactor] plants

Creators

  • 1. Pickard, Lowe and Garrick, Newport Beach, CA (USA)

Description

The purpose of this paper is to examine important trends in probabilistic risk assessment (PRA) results for pressurized water reactor (PWR) plants with large, dry, subatmospheric containments. Of particular interest in this paper is the class of potential accident scenarios involving a postulated large early release. This paper examines level-3 PRA results from pressurized water reactor to examine important trends in the estimation of early release

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
60
Series
Trans. Am. Nucl. Soc.
Journal Page Range
402-404
ISSN
0003-018X
CODEN
TANSA

Conference

Title
Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
Dates
26-30 Nov 1989.
Place
San Francisco, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22012634
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT SYSTEMS; ECCS; FISSION PRODUCT RELEASE; LOSS OF COOLANT; MISSILE PROTECTION; PROBABILITY; PWR TYPE REACTORS; RADIATION DOSES; REACTOR CORE DISRUPTION; REACTOR SAFETY; RISK ASSESSMENT; SEABROOK-1 REACTOR; SEABROOK-2 REACTOR; SOURCE TERMS; STEAM GENERATORS; SURRY-1 REACTOR; SURRY-2 REACTOR; SURRY-3 REACTOR; SURRY-4 REACTOR; US NRC
Descriptors DEC
ACCIDENTS; BOILERS; CONTAINMENT; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; US ORGANIZATIONS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-891103--.