核电站整体实验回路PMK-NVH装置模拟的小破口失水事故的分析计算

ANALYSIS OF THE PMK-NVH INTEGRAL SYSTEM FACILITY FOR SMALL BREAK LOCA USING RELAP5/MOD1 CODE

摘要: <正> 一、前言核电站的假想小破口失水事故是核电安全热工水力分析的一个重要方面,特别是在美国三里岛事故后,更加引起人们的重视。在国际原子能机构的组织下,作者根据匈牙利科学院提供的资料,使用核电安全分析

Abstract: The PMK-NVH test facility and the SBLOCA experiment conditions areintroduced. The prediction of this experiment is done and the results are comparedwith the experimental data. some conclusions about this calculation and the faci-lity capacity are given.