[科技报告]DE  Ireland, J. R.17

摘要: This paper describes the overall pressurized thermal shock (PTS) program at Los Alamos with emphasis on TRAC-PF1 calculations of severe overcooling transients for the Oconee-1 pressurized water reactor (PWR). A summary of results ... 展开

翻译摘要
作者 Ireland, J. R.  
原报告号 DE84001701 总页数 17
主办者 Technical Information Center Oak Ridge Tennessee
报告分类号 [77H - Reactor Engineering & Nuclear Power Plants]
报告类别/文献类型 DE / NTIS科技报告
关键词 Oconee-1 Reactor   Pressure Vessels   Reactor Safety   Computer Calculations   Computer Codes   Computerized Simulation   Primary Coolant Circuits   Ruptures   T Codes   Thermal Shock   Transients  
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