STEAM LINE BREAK ANALYSIS COMPARISON TO THE WOLF CREEK UPDATED SAFETY ANALYSIS REPORT

被引：3
|
作者：
NEISES, GJ
GARRETT, TJ
机构：
[1] Wolf Creek Nuclear Operating Corp, Wichita, KS
来源：
NUCLEAR TECHNOLOGY | 1991年 / 93卷 / 01期
关键词：
D O I：
10.13182/NT91-A34515
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：
A steam line break transient is analyzed for the Wolf Creek Generating Station using RETRAN02/MOD3. The RETRAN analysis results and the modeling approaches used for the steam line break transient are described. The results of this analysis are compared with the results of the Wolf Creek Updated Safety Analysis Report (USAR). The steam line break results presented in the USAR comparison include mixing between the affected and unaffected loops in the reactor vessel, boron tracking in the reactor coolant system, and sensitivity studies of various parameters.
引用
收藏
页码：22 / 35
页数：14
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