西安脉冲反应堆再淹没特性研究  

Study on Characteristics of Xi’an Pulsed Reactor in Reflood Stage

作　　者：王子铭 傅俊森 肖瑶[1] 田晓艳[2] 苏春磊[2] 李达[2] 顾汉洋[1] Wang Ziming;Fu Junsen;Xiao Yao;Tian Xiaoyan;Su Chunlei;Li Da;Gu Hanyang(School of Nuclear Science and Engineering,Shanghai Jiao Tong University,Shanghai,200240,China;Northwest Institute of Nuclear Technology,Xi'an,710024,China)

机构地区：[1]上海交通大学核科学与工程学院,上海200240 [2]西北核技术研究所,西安710024

出　　处：《核动力工程》2024年第3期60-67,共8页Nuclear Power Engineering

基　　金：国家自然科学基金(12322510,12075150,12275174);上海市青年科技启明星计划(22QA1404500)。

摘　　要：再淹没过程是失水事故重要环节,明确再淹没过程中堆芯瞬态热工特性对破口失水事故安全分析极为关键。本研究基于子通道分析程序CTF,针对西安脉冲反应堆典型大、小破口失水事故中再淹没过程开展了瞬态分析计算。分析中将堆芯依据功率划分为8个通道,获得了骤冷前沿和堆芯温度的时空分布特性,分析了不同位置燃料棒在各高度的包壳与燃料棒中心温度变化规律。研究结果表明,外围燃料棒相较于中心最热棒温度更低且更早被完全冷却;大、小破口失水事故工况下冷却剂均能完全淹没堆芯,使堆芯完全冷却,大破口失水事故工况下因衰变功率更大,堆芯被完全冷却所需时间更长;大破口失水事故工况下包壳失效风险较小,小破口失水事故包壳失效风险相较于大破口失水事故工况更高,大、小破口失水事故工况下均不会发生燃料芯块熔毁。Reflood process is an important part of LOCA,and it is crucial to identify the transient thermal characteristics of core during reflood process for the safety analysis of break accident.Based on the subchannel analysis code CTF,the transient analysis and calculation are carried out for the reflood process of Xi'an pulsed reactor in typical large and small break loss of coolant accidents.In the analysis,the core is divided into eight channels based on power.The spatiotemporal distribution characteristics of the quenching front and core temperature are obtained,and the temperature changes of the cladding and fuel rod center at different heights of fuel rods at different positions are analyzed.The results show that the temperature of the outer fuel rods is lower and completely cooled earlier than that of the hottest rod at the center.Under both large and small break conditions,the coolant can completely submerge the core,allowing it to cool completely.Under large break conditions,due to higher decay power,it takes longer for the core to be completely cooled.The risk of cladding failure is relatively low under large break conditions,while the risk of cladding failure in small break accidents is higher compared to large break conditions.Fuel pellet melting will not occur under both large and small break conditions.

关 键 词：脉冲堆 再淹没 堆芯温度 子通道程序 安全特性 

分 类 号：TL33[核科学技术—核技术及应用]