[科技报告]DE  Cahalan, J. E., Wei, T. Y. C.15

摘要: The SAS4A and SASSYS computer codes are being developed at Argonne National Laboratory for transient analysis of liquid metal cooled reactors. The SAS4A code is designed to analyse severe loss-of-coolant flow and overpower acciden... 展开

翻译摘要
作者 Cahalan, J. E.   Wei, T. Y. C.  
原报告号 DE90010056 总页数 15
主办者 Technical Information Center Oak Ridge Tennessee
报告分类号 [77H - Reactor Engineering & Nuclear Power Plants97Q - Selected Studies In Nuclear Technology]
报告类别/文献类型 DE / NTIS科技报告
关键词 LMFBR Type Reactors   Loss of Coolant   Computerized Simulation   Corium   Feedwater   Fission Product Release   Fuel Cans   Heat Transfer   Hydraulics   Pipes   Pumps   Reactor Components   Reactor Cooling Systems   Reactor Safety   S Codes   Steam Generators   Meetings   EDB/210500   EDB/220900   EDB/990200    
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