Modified RELAP4/MOD7 code and large break loss of water accident analysis

被引：0

作者：

Luo, Bangqi ^{[1
]}

机构：

[1] Beijing Inst of Nuclear Engineering, Beijing, China

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 1994年 / 15卷 / 01期

关键词：

Computer software - Nuclear engineering - Nuclear power plants - Numerical analysis - Transients;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

The RELAP4/MOD7 is a large transient thermohydraulic calculation code which is licensed by American NRC for engineering examination. There are some errors in RELAP4/MOD7 code version used in China. Some improvements for code application and development, such as reset, reedition, etc. has been made and some modifications for applied physicomathematical model had also been adopted. The calculation results of large break loss of water accident using modified RELAP4/MOD7 code is in agreement with foreign calculation result of same kind nuclear plant. Now, this code has been used to analyze the large break loss of water accident in the 2nd phase construction of Qinshen Nuclear Power Plant and a satisfactory result has been obtained.

引用

页码：7 / 11