Verification of relap5/mod3.2 critical heat transfer computational method by experiments performed on the ks facility

被引:0
|
作者
D. A. Afremov
D. A. Yashnikov
机构
[1] Dollezhal Research and Development Institute of Power Engineering (NIKIET),
来源
Atomic Energy | 2011年 / 110卷
关键词
Heat Flux; Critical Heat Flux; Mixed Packing; Thermohydraulic Calculation; Fuel Assembly Model;
D O I
暂无
中图分类号
学科分类号
摘要
The computational results obtained with the RELAP5/mod3.2 code for critical heat transfer are compared with experimental data obtained on the KS facility for RBMK fuel assembly models. The confidence interval is constructed for the correction factor to the computed critical heat flux.
引用
收藏
页码:328 / 331
页数:3
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