RELAP5/MOD3 analysis of transient steam-generator behavior during turbine trip test of a prototype fast breeder reactor MONJU

被引：0

作者：

Japan Nuclear Energy Safety Organization , Safety Analysis and Evaluation Division, Kamiya-cho MT Bldg., 4-3-20, Minato-ku, Tokyo, 105-0001, Japan ^{[1
]}

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来源：

| 1600年 / 2006期

关键词：

Compendex;

D O I：

Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14

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学科分类号：

摘要：

Breeder reactors - Hydraulics - Mass transfer - Nuclear energy - Two phase flow - Water supply

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