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Burns, R.D. III; Scott, J.H.
Los Alamos Scientific Lab., NM (USA)1980
Los Alamos Scientific Lab., NM (USA)1980
AbstractAbstract
[en] Recent work to identify the most likely beyond design-basis-accident (DBA) sequences which could occur in US commercial pressurized water reactors (PWRs) is summarized. These are defined here as postulated sequences in which all events have been observed separately in US reactors. Further, they involve an initiating failure and one or two additional equipment failures or human errors. These sequences are deemed more likely than others in which all failure events have not been observed or which involve more failure events. The postulated accident sequences are taken from the larger set contained in the reactor safety study (WASH-1400). Reactor operating experience is from government reports summarizing licensee event reports
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1980; 4 p; ANS thermal reactor safety meeting; Knoxville, TN, USA; 8 - 11 Apr 1980; CONF-800403--6; Available from NTIS., PC A02/MF A01
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Report
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Conference
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