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
作者 | Cahalan, J. E. Wei, T. Y. C. | ||
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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 |