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作 者:林萍 杨森皓 陈旭鹏 银建中[1] 韩志远[2] 谢国山[2] LIN Ping;YANG Senhao;CHEN Xupeng;YIN Jianzhong;HAN Zhiyuan;XIE Guoshan(School of Chemical Engineering,Dalian University of Technology,Dalian 116024,China;China Special Equipment Inspection and Research Institute,Beijing 100029,China)
机构地区:[1]大连理工大学化工学院,辽宁大连116024 [2]中国特种设备检测研究院,北京100029
出 处:《压力容器》2023年第5期34-43,共10页Pressure Vessel Technology
基 金:国家重点研发计划项目(2018YFC0808805)。
摘 要:研究了承压热冲击(PTS)事故发生时,变化的堆芯衰变热对反应堆压力容器(RPV)安全分析的影响。基于ACP1000三回路反应堆压力容器,对25 cm 2小破口失水事故工况应用三维流固热耦合方法进行模拟。计算了事故下2000 s内堆芯衰变热随时间的变化函数,得到变化堆芯衰变热影响下冷却剂经过堆芯后的温升、三回路模型安注流动轨迹、确定RPV环腔内温度最低点(冷点)的位置,并在此处施加裂纹影响,得到变化堆芯衰变热影响下应力强度因子分析结果,并与1 MW/m 3堆芯衰变热结果进行比较。结果表明,在本瞬态工况下变化的堆芯衰变热对流经的冷却剂有明显的升温作用,RPV内壁应力也有16.02%的增幅,应力强度因子有30.1%的增幅。The influence of varying core decay heat on safety analysis of the reactor pressure vessel(RPV)during the occurrence of pressurized thermal shock(PTS)accidents was studied.Three-dimensional fluid-solid thermal coupling method was applied to simulate the 25 cm 2 small break loss of coolant accident in ACP1000.The change function of core decay heat in 2000 s in case of an accident was calculated,the temperature rise of the core after the coolant flows through the core under the influence of varying core decay heat and the three-loop model injection flow path were obtained,the position of the lowest point(cold point)in annular cavity of RPV was determined,crack influence was applied here,the analysis results of stress intensity factor under the influence of varying core decay heat were obtained,and compared with the results of 1 MW/m 3 core decay heat.The results show that the varying core decay heat under this transient condition has an obvious heating up effect on the coolant flowing through the core,the inner wall stress of RPV also increases by 16.02%,and the stress intensity factor increases by 30.1%.
关 键 词:反应堆压力容器 堆芯衰变热 小破口失水事故 承压热冲击
分 类 号:TH49[机械工程—机械制造及自动化] TL351.6[核科学技术—核技术及应用] TL333
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