期刊文献+

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
原文传递
导出
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.
作者 王子铭 傅俊森 肖瑶 田晓艳 苏春磊 李达 顾汉洋 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)
出处 《核动力工程》 EI CAS CSCD 北大核心 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)。
关键词 脉冲堆 再淹没 堆芯温度 子通道程序 安全特性 Pulsed reactor Reflood Core temperature Subchannel code Safety features
  • 相关文献

参考文献14

二级参考文献36

  • 1陈立新,张颖,陈伟,单建强,石海松,朱养妮.子通道程序PRTHA在西安脉冲堆上的应用[J].核动力工程,2003,24(S2):56-59. 被引量:6
  • 2陈立新,赵柱民,袁建新.西安脉冲堆热工水力分析与脉冲特性分析[J].核动力工程,2006,27(6):1-4. 被引量:3
  • 3谢国锋,何旭洪,童节娟,郑艳华.响应面方法计算HTR-10余热排出系统物理过程的失效概率[J].物理学报,2007,56(6):3192-3197. 被引量:19
  • 4魏永仁,唐钢,吴清,等.PRC-Ⅱ脉冲反应堆事故分析[R].北京:原子能出版社,1998.
  • 5核工业标准化研究所.中华人民共和国核行业标准EJ/T745-2001轻水堆核燃料衰变热功率的计算[S].北京:国防科学技术工业委员会,2001.
  • 6General Atomic Company. Safety analysis reprot for the TRIGA MARK II reactor operating with a steady-state power of 1 000 kW or pulsed reactivity insertions of $ 3.00[R]. San Diego, USA: General Atomic Company, 1977.
  • 7陶文铨,数值传热学,1988年
  • 8徐济--,沸腾传热和气液两相流,1994年,1页
  • 9赵兆颐,反应堆热工流体力学,1993年,1页
  • 10彭木彰,核动力工程,1984年,5卷,6期,78页

共引文献30

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部