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高通量工程试验堆RELAP5建模与试验评价 被引量:1

RELAP5 Model and Test Evaluation of High Flux Engineering Test Reactor
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摘要 出口母管破口失水事故(LOCA)是高通量工程试验堆(HFETR)安全评价的重要始发事件之一,本文基于RELAP5程序,建立了HFETR的数值计算模型,模拟了HFETR的LOCA试验工况;通过手动全开HFETR除气系统DN50阀模拟出口母管失水试验,获得了反应堆进出口压力、容补器压力和破口流量的变化,并通过试验数据验证了RELAP5程序的计算结果合理性,结果表明:RELAP5计算结果和实验结果吻合较好,最大相对误差为7.4%,说明利用RELAP5程序模拟低温中压压水型研究堆的系统瞬变可行。 In the safety assessment of High Flux Engineering Test Reactor(HFETR), the Loss of-Coolant Accident(LOCA) is one of the most important initial events. This paper establishes a numerical calculation model of HFETR reactor based on RELAP5, and simulates the testing case of LOCA. By opening the DN50 valve of primary loop degassing system, the LOCA was simulated. The parameters of reactor inlet and outlet pressures, regulator pressure, and breaking flow rate were tested. Meanwhile, through comparison and analysis of testing data and calculation data, the rationality of the calculation result of RELAP5 program was evaluated. The results show that the RELAP5 calculation result is in good agreement with the experimental results, and the maximum relative error is 7.4%. Those results imply that it is feasible to use the RELAP5 program to simulate the system transients at a low-pressure, pressurized water reactor, such as HFETR.
作者 李海涛 周春林 邹德光 张江云 王文龙 肖盾 蒋汀岚 Li Haitao;Zhou Chunlin;Zou Deguang;Zhang Jiangyun;Wang Wenlong;Xiao Dun;Jiang Tinglan(Nuclear Power Institute of China, Chengdu, 610213, China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2018年第S2期112-115,共4页 Nuclear Power Engineering
关键词 高通量工程试验堆(HFETR) RELAP5 失水事故(LOCA) 试验评价 High Flux Engineering Test Reactor (HFETR) RELAP5 Loss-of-Coolant Accident(LOCA) Test evaluation
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