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HFETR 2000 kW高温高压考验回路主泵断电事故瞬态特性分析

Transient Characteristics Analysis of 2000 kW High Temperature and High Pressure Test Loop of HFETR during Loss of Power Accident of Main Pump
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摘要 为了研究高通量工程试验堆(HFETR)内2000 kW高温高压考验回路在主泵断电事故过程中的安全特性,基于RELAP5程序建立了考验回路的仿真模型,采用验证后的模型开展了主泵断电事故瞬态特性分析。计算结果表明,在主泵断电事故过程中,主泵高速工况会切换至2台事故泵低速工况,流量下降较快并最终稳定至初始流量的一半,燃料包壳在4.34 s达到峰值温度763 K;之后由于功率的不断下降,包壳温度随之不断下降;事故过程中最小偏离泡核沸腾比大于1.3,表明不会发生偏离泡核沸腾,满足安全要求。 In order to study the safety characteristics of 2000 kW high temperature and high pressure test loop in high flux engineering test reactor(HFETR)in the process of loss of power accident of main pump,the simulation model of test loop is established based on RELAP5 code,and the transient characteristics of loss of power accident of main pump are analyzed by using the verified model.The calculation results show that in the process of loss of power accident of main pump,the high-speed working condition of the main pump switches to the low-speed working condition of the two accident pumps,the flow rate decreases rapidly and finally stabilizes to half of the initial flow rate,and the fuel cladding reaches a peak temperature of 763 K at 4.34 s;Then,due to the continuous decline of power,the cladding temperature decreases continuously;The minimum departure from nucleate boiling ratio during the accident is greater than 1.3,which indicates that departure from nucleate boiling will not occur and meets the safety requirements.
作者 刘文斌 宋霁阳 邓才玉 康长虎 向玉新 宋雨鸽 刘畅 郭雨非 邢如均 Liu Wenbin;Song Jiyang;Deng Caiyu;Kang Changhu;Xiang Yuxin;Song Yuge;Liu Chang;Guo Yufei;Xing Rujun(Nuclear Power Institute of China,Chengdu,610213,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2022年第3期74-77,共4页 Nuclear Power Engineering
基金 中核集团青年英才项目(CNNC-2020-08)。
关键词 RELAP5 辐照考验回路 主泵断电事故 高通量工程试验堆(HFETR) RELAP5 Irradiation test loop Loss of power accident for main pump High flux engineering test reactor(HFETR)
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