skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: BWR containment failure analysis during degraded-core accidents

Abstract

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.

Authors:
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
5338909
Report Number(s):
CONF-820609-55
ON: DE82017432; TRN: 82-015961
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Conference
Resource Relation:
Conference: American Nuclear Society annual meeting, Los Angeles, CA, USA, 6 Jun 1982
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; CONTAINMENT SYSTEMS; FAILURE MODE ANALYSIS; REACTOR ACCIDENTS; REACTOR SAFETY; THERMAL STRESSES; ACCIDENTS; CONTAINMENT; ENGINEERED SAFETY SYSTEMS; REACTORS; SAFETY; STRESSES; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled

Citation Formats

Yue, D D. BWR containment failure analysis during degraded-core accidents. United States: N. p., 1982. Web.
Yue, D D. BWR containment failure analysis during degraded-core accidents. United States.
Yue, D D. 1982. "BWR containment failure analysis during degraded-core accidents". United States. https://www.osti.gov/servlets/purl/5338909.
@article{osti_5338909,
title = {BWR containment failure analysis during degraded-core accidents},
author = {Yue, D D},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/5338909}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jun 06 00:00:00 EDT 1982},
month = {Sun Jun 06 00:00:00 EDT 1982}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: