秦山核电厂燃料包壳PCMI阈值分析  

Analysis of PCMI Threshold of Fuel Rod for Qinshan Nuclear Power Plant

作　　者：张应超[1] 陈彭[1] 

机构地区：[1]中国原子能科学研究院反应堆工程研究设计所,北京102413

出　　处：《原子能科学技术》2000年第z1期86-89,共4页Atomic Energy Science and Technology

摘　　要：利用欧共体提供的日本燃料元件行为分析程序FEMAXI Ⅳ ,分析秦山核电厂燃料芯块与包壳局部机械相互作用 (PCMI)的应力水平 ,评价PCMI破坏的安全裕量。通过计算应力阈值图 ,确定秦山核电厂燃料棒的运行功率阈值图 ,并由此得出在控制棒不可控抽出事故瞬态下 ,功率裕量为 147W /cm ,相应的应力裕量为 2 63MPa。The Japanese fuel behavior analysis code FEMAXI-Ⅳ provided by OECD is used to calculate the stress level of Qinshan Nuclear Power Plant fuel rod under pellet clad mechanical interaction (PCMI) and to evaluate the safety margin of PCMI.The threshold of rod power is obtained after the determination of threshold of local hoop stress.The safety margin of linear power is 147 W/cm and the safety margin of local hoop stress is 263 MPa under the accident condition of unanticipated control rod withdrawing according to the threshold.

关 键 词：燃料棒 周向应力 PCMI 

分 类 号：TL[核科学技术]