摘要
为估算低温核供热堆的第一类密度波不稳定(Type-ⅠDWO)边界,以确定其微沸腾运行模式的参数区间,本文建立了低温核供热堆NHR200相似性实验回路HRTL200的RELAP5数值模型。通过对比模拟结果与实验结果,评价了RELAP5/MOD3.2程序模拟Type-ⅠDWO的一般特性以及预测不稳定边界的能力,分析了进、出口阻力系数、相间摩擦对模拟结果的影响。结果表明,RELAP5程序模拟Type-ⅠDWO的一般特性与实验符合较好;运行压力不高于25 bar(1 bar=10^(5) Pa)时,程序计算的不稳定边界的过冷度边界值与实验值偏差在3 K以内;运行压力大于30 bar时,采用准确的相间摩擦关系式可以改善预测结果。因此,选取与回路相匹配的相间摩擦关系式后,RELAP5程序可以用于模拟和预测Type-ⅠDWO。
In order to estimate the unstable(Type-ⅠDWO)boundary of Type-Ⅰdensity wave of low temperature nuclear heating reactor and determine the parameter interval of its slight-boiling mode,the RELAP5 numerical model of NHR200 similarity experimental loop HRTL200 of low temperature nuclear heating reactor is established in this paper.By comparing the simulation results with the experimental results,the general characteristics of RELAP5/MOD3.2 program for simulating Type-ⅠDWO and the ability to predict the unstable boundary are evaluated,and the effects of inlet and outlet resistance coefficients and interphase friction on the simulation results are analyzed.The results show that the general characteristics of Type-ⅠDWO simulated by RELAP5 program are in good agreement with the experiment;When the operating pressure is not higher than25 bar(1 bar=10^(5) Pa),the deviation between the degree of subcooling boundary value of the unstable boundary calculated by the program and the experimental value is within 3 K;when the operating pressure is greater than 30 bar,the accurate interphase friction relationship can improve the prediction results.Therefore,RELAP5 program can be used to simulate and predict Type-ⅠDWO after selecting the interphase friction relationship matching the circuit.
作者
滕辰
解衡
贾海军
Teng Chen;Xie Heng;Jia Haijun(Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing,100084,China;Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education,Tsinghua University,Beijing,100084,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2021年第6期65-71,共7页
Nuclear Power Engineering
基金
国家重点研发计划(2018YFB190051)。
