GAO Yongjian HE Yinbiao CAO Ming SHEN Rui TAO Hongxin. Stress analysis and assessment of RPV core support pads and surround bottom head[J]. Nuclear techniques, 2013, 36(4): 040659
GAO Yongjian HE Yinbiao CAO Ming SHEN Rui TAO Hongxin. Stress analysis and assessment of RPV core support pads and surround bottom head[J]. Nuclear techniques, 2013, 36(4): 040659 DOI: 10.11889/j.0253-3219.2013.hjs.36.040659.
Stress analysis and assessment of RPV core support pads and surround bottom head
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 CAP1000 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.
Benefit for the analysis of P-T limit curve of a home-made RPV using RTT0 instead of RTNDT
Structural studies on fluid selenium using synchrotron radiation
Sealing behavior simulation technology research for CPR1000 reactor pressure vessel
Research progress and recommendations on reactor pressure vessel integrity under hypothetical core melt down accident
Research on structural integral assessment of cylinders with circumference cracks under pressurized thermal shock based on probabilistic fracture mechanics
Related Author
HE Yinbiao
HUI Hu
LI Hui
XUAN Fuzhen
CAO Yupeng
HONG Xinguo1 INUI Masanori2 TAMURA Kozaburo3 1
乾雅祝
田村刚三郎
Related Institution
Key Laboratory of Pressure System and Safety, Ministry of Education, East China University of Science and Technology
Department of Component Research and Design,Shanghai Nuclear Engineering Research and Design Institute
Institute of High Energy Physics, Chinese Academy of Sciences, Beijing 100039) 2