原子能科学技术2012，Vol.46Issue(z1)：206-210,5.
池式研究堆自然循环能力试验及数值模拟
Natural Circulation Capacity Experiment and Numerical Simulation for Pool-Type Research Reactor
黄洪文 1刘汉刚 1杨晓斌 1钱达志 1徐显启 1黄文 1张旸1
作者信息
- 1. 中国工程物理研究院核物理与化学研究所,四川绵阳621900
- 折叠
摘要
Abstract
The natural circulation capacity is the important parameter that characterizes the safety capability of a nuclear reactor. In order to analysis the passive safety of a pool-type research reactor, and determine the extreme levels of heat-carrying capacity under natural circulation condition, according to the special core structure, a method was proposed to carry out natural circulation experiment, and a software was developed to analysis the natural circulation capability. The calculation results of core flow satisfy experimental values well, and the relative deviation is less than 1. 6%. Under the condition the pool water temperature is 40℃, the natural circulation capacity of the reactor is no less than 710 kW according to the calculation result of the code. It indicates that this pool reactor has good passive safety ability.关键词
自然循环能力/池式研究堆/热工水力程序Key words
natural circulation capacity/ pool-type research reactor/ thermal-hydraulic code分类
能源科技引用本文复制引用
黄洪文,刘汉刚,杨晓斌,钱达志,徐显启,黄文,张旸..池式研究堆自然循环能力试验及数值模拟[J].原子能科学技术,2012,46(z1):206-210,5.
