节点文献
堆内构件假想堆芯跌落事故分析
Reactor Vessel Internals Hypothetical Core Drop Analysis
【作者】 冯少东; 张明; 朱焜; 薛国宏; 李源; 陈惠亮;
【Author】 FENG Shaodong ZHANG Ming ZHU Kun XUE Guohong Li Yuan CHEN Huiliang (Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200433, China)
【机构】 上海核工程研究设计院;
【摘要】 堆内构件是反应堆冷却剂系统中的重要设备之一。堆芯跌落事故是会造成吊篮及支承结构跌落,通过防断组件对压力容器底封头内表面造成冲击,该冲击能量由防断组件缓冲器的塑性形变完全吸收。采用Ludwik扩展来模拟材料应力-应变曲线,考虑堆芯自重、浮力、热膨胀等因素的影响,计算了材料在冷态和热态条件下的应变率,据此得到了堆芯跌落的冲击载荷和跌落高度,评价了其对压力容器结构完整性和堆芯上板定位销功能性的影响,并对受压组件进行了稳定性分析。
【Abstract】 The reactor vessel internals (RVI) mounted inside of reactor vessel provide the direct support and restraint of the core. A core drop accident causes the core barrel and supporting structure to drop and impact on the bottom of the reactor vessel. The energy from the core drop is assumed to be absorbed by the plastic strain in the "necked-down" portion of the energy absorbers. The stress-strain curves applicable to the material are approximated by Ludwik’s expression. Considering the core deadweight, buoyancy force and heat expansion, material train ratios for both cold and hot conditions are calculated. Vessel impact load and elongation of energy absorber are determined. Finally, the scram function and buckling of compressive assemblies are investigated.
【Key words】 Core Drop; Ludwik Expand; Stress-Strain Curve; Strain Ratio;
- 【会议录名称】 第十七届全国反应堆结构力学会议论文集
- 【会议名称】第十七届全国反应堆结构力学会议
- 【会议时间】2012-10-15
- 【会议地点】中国上海
- 【分类号】TL343
- 【主办单位】中国力学学会反应堆结构力学专业委员会