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
作者 | Ireland, J. R. | ||
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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 |