核释热瞬态特性模拟实验研究  

Experimental Study of Nuclear-heat- release Transient Characteristics Simulation

作　　者：吴小航[1] 赵华[1] 蒋序伦[1] 

机构地区：[1]中国核动力研究设计院空泡物理和自然循环国防科技重点实验室,成都610041

出　　处：《核动力工程》2001年第2期118-121,154,共5页Nuclear Power Engineering

摘　　要：提出了一种在用电加热模拟核释热瞬态特性的方法，该方法采用计算机模拟多谱勒效应和慢化剂温度效应，并控制电加热元件的加热功率。应用该方法进行了升功率和降流量两项实时模拟实验，将实验结果与用 Retran 02程序计算的结果进行了比较，结果证明，用本文中的方法模拟核释热的瞬态特性是可行的。This paper introduces a method to simulate nuclear-heat-release with electric heating rod on test facility. In this method, heating power of electric heating rod is controlled with a computer, which simulates doppler effect and moderator temperature effect. By this method, two real-time simulating experiments, raising power and lowering flow, have been performed. Experimental results are compared with results of analysis using Retran-02 code. As a result of the comparison, it is shown that the method is feasible in simulating nuclear-heat-release transient characteristics.

关 键 词：核释热 瞬态特性 电加热 反应性反馈 模拟实验 反应堆 热工水力实验 

分 类 号：TL33[核科学技术—核技术及应用]