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TRAC-PF1/MOD2 best-estimate analysis of a large-break LOCA in a 15 (times) 15 generic four-loop Westinghouse nuclear power plant.

机译：TRaC-pF1 / mOD2最佳估算分析15（次）15通用四回路西屋核电厂的大型LOCa。

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Calculations of a large-break loss-of-coolant accident (LOCA) in a 15 (times) 15 generic four-loop Westinghouse nuclear power plant with both the TRAC-PF1/MOD1 and TRAC-PF1/MOD2 computer codes will be presented. The Transient Reactor Analysis Code (TRAC) ...

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作者
J. W. Spore J. C. Lin N. M. Schnurr J. R. White M. C. Cappiello;
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年度 1992
页码 1-42
总页数 42
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Computerized Simulation; EDB/210200; EDB/220900; EDB/990200; Heat Transfer; Hydraulics; Loss of Coolant; Meetings; PWR Type Reactors; Reactor Safety; T Codes;

机译：计算机模拟; EDB / 210200; EDB / 220900; EDB / 990200;传热;液压;冷却液损失;会议; pWR型反应堆;反应堆安全; T代码;

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TRAC-PF1/MOD2 best-estimate analysis of a large-break LOCA in a 15 (times) 15 generic four-loop Westinghouse nuclear power plant.

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