Published June 6, 1982 | Version v1
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BWR containment failure analysis during degraded-core accidents

Creators

Description

This paper presents a containment failure mode analysis during a spectrum of postulated degraded core accident sequences in a typical 1000-MW(e) boiling water reactor (BWR) with a Mark-I wetwell containment. Overtemperature failure of containment electric penetration assemblies (CEPAs) has been found to be the major failure mode during such accidents

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01 as DE82017432.

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Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
CONF-820609--55

Conference

Title
American Nuclear Society annual meeting.
Dates
6 - 11 Jun 1982.
Place
Los Angeles, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
14724001
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CONTAINMENT SYSTEMS; FAILURE MODE ANALYSIS; REACTOR ACCIDENTS; REACTOR SAFETY; THERMAL STRESSES
Descriptors DEC
ACCIDENTS; CONTAINMENT; REACTORS; SAFETY; STRESSES; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; WATER COOLED REACTORS; WATER MODERATED REACTORS