摘要
华龙一号堆腔注水冷却系统(CIS)投入时,反应堆压力容器(RPV)外壁将经历剧烈的温度波动并同时承受较高的内压载荷。为了保证RPV在这种工况下的结构完整性,采用断裂力学有限元方法进行了RPV承压热冲击(PTS)计算及评定,通过疲劳裂纹扩展计算获得了堆芯筒体和下封头区域寿期末的最终裂纹尺寸。PTS瞬态载荷作用下的应力强度因子修正值与相应限值的最大比值约为0.874,满足RCC-M规范要求。研究结果表明,RPV在CIS投用时不会出现断裂失效。
When the cavity injection and cooling system(CIS)of HPR1000 nuclear power unit is put into operation,the outer wall of the reactor pressure vessel(RPV)will experience severe temperature fluctuations while also withstanding high internal pressure loads.In order to ensure the structural integrity of RPV under such conditions,the finite element method of fracture mechanics is used to perform the calculations and assessment of pressurized thermal shock(PTS).The estimated final crack sizes of the core barrel and the lower of head region at the end of life are obtained by fatigue crack propagation calculation.The maximum ratio of the correction value of the stress intensity factor under the PTS transient load to the corresponding limit is about 0.874,which meets the requirements of the RCC-M rule.The results indicated that the fracture failure of RPV would not occur when the CIS is applied.
作者
郑斌
朱大欢
卢岳川
孙英学
石凯凯
谢海
Zheng Bin;Zhu Dahuan;Lu Yuechuan;Sun Yingxue;Shi Kaikai;Xie Hai(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2019年第S02期121-125,共5页
Nuclear Power Engineering
