摘要
堆芯支承块用以限制堆芯吊篮的周向转动,其结构完整性影响反应堆的安全运行。为保证堆芯支承块的结构完整性,本文建立CAP1000反应堆压力容器下封头、堆芯支承块及部分筒体的三维有限元模型,进行热分析、结构分析、疲劳分析及断裂分析,并根据ASME B&PVC-III-NB-3200和ASME B&PVC-III-1附录G的相关规定对计算结果进行评定。结果表明,堆芯支承块及附近下封头满足上述规范的相关要求。本文所采用的分析方法可应用于百万级以上核电厂反应堆压力容器的堆芯支承块的分析。
Background： The core support pads were used to limit circumferential rotation of core barrel, and the structure integrity of the core support pads was an important factor to the safe operation of nuclear power plant. Purpose： To ensure the structure integrity of the core support pads. Methods： Three-dimensional FEA model for bottom head, core support pads and part cylinder of CAP 1000 RPV was established. Thermal analysis, static analysis, fatigue analysis and fracture analysis were performed. The analysis results were evaluated according to ASME B＆PVC-III-NB-3200 and ASME B＆PVC-Ⅲ-1-Appendix G. Results： The evaluation indicated that the core support pads and surround bottom head could satisfy related requirements of above code. Conclusions： The analysis methodology used in this paper could also be applied to the core support pads of RPV for above 1000 MW nuclear power plant.
出处
《核技术》
CAS
CSCD
北大核心
2013年第4期306-312,共7页
Nuclear Techniques
关键词
反应堆压力容器
堆芯支承块
结构分析
疲劳分析
断裂分析
Reactor pressure vessel
Core support pads
Structural analysis
Fatigue analysis
Fracture analysis
