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AbstractAbstract
[en] Sodium releases from postulated pipe ruptures, as well as failures of sodium handling equipment in liquid metal fast breeder reactors, may lead to substantial pressure-temperature transients in the sodium system cells, as well as in the reactor containment building. Sodium fire analyses are currently performed with analytical tools, such as the SPRAY, SOMIX, SPOOL-FIRE and SOFIRE-II codes. A review and evaluation of the state-of-the-art in sodium fire analysis is presented, and suggestions for further improvements are made. This work is based, in part, on studies made at Brookhaven National Laboratory during the past several years in the areas of model development and improvement associated with the accident analyses of LMFBRs
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1978; 13 p; Specialists' meeting on sodium fires and prevention; Aix-en-Provence, France; 20 - 24 Nov 1978; CONF-781173--1; Available from NTIS., PC A02/MF A01
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Report
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Conference
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