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Identification and assessment of BWR in-vessel severe accident mitigation strategies
Author(s) -
S.A. Hodge,
J.C. Cleveland,
T.S. Kress,
M. Petek
Publication year - 1992
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/10102664
Subject(s) - accident management , boiling water reactor , reactor pressure vessel , work (physics) , accident (philosophy) , containment (computer programming) , corium , environmental science , risk analysis (engineering) , forensic engineering , engineering , nuclear engineering , computer science , business , mechanical engineering , heat transfer , philosophy , physics , epistemology , thermodynamics , programming language
This report provides the results of work carried out in support of the US Nuclear Regulatory Commission Accident Management Research Program to develop a technical basis for evaluating the effectiveness and feasibility of current and proposed strategies for boiling water reactor (BWR) severe accident management. First, the findings of an assessment of the current status of accident management strategies for the mitigation of in-vessel events for BWR severe accident sequences are described. This includes a review of the BWR Owners' Group Emergency Procedure Guidelines (EPGSs) to determine the extent to which they currently address the characteristic events of an unmitigated severe accident and to provide the basis for recommendations for enhancement of accident management procedures. Second, where considered necessary, new candidate accident management strategies are proposed for mitigation of the late-phase (after core damage has occurred) events. Finally, recommendations are made for consideration of additional strategies where warranted, and two of the four candidate strategies identified by this effort are assessed in detail: (1) preparation of a boron solution for reactor vessel refill should control blade damage occur during a period of temporary core dryout and (2) containment flooding to maintain the core debris within the reactor vessel if themore » injection systems cannot be restored.« less

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