VERIFICATION OF RELAP5/mod3.2 CRITICAL HEAT TRANSFER COMPUTATIONAL METHOD BY EXPERIMENTS PERFORMED ON THE KS FACILITY

被引：0
|
作者：
Afremov, D. A. [1 ]
Yashnikov, D. A. [1 ]
机构：
[1] Dollezhal Res & Dev Inst Power Engn NIKIET, Moscow, Russia
来源：
ATOMIC ENERGY | 2011年 / 110卷 / 05期
关键词：
Heat Flux; Critical Heat Flux; Mixed Packing; Thermohydraulic Calculation; Fuel Assembly Model;
D O I：
10.1007/s10512-011-9430-4
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
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：4
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