YAO Yangui NING Dong WU Zhiwei CAO Ming XIE Yongcheng HE Yinbiao YAO Weida. Research progress and recommendations on reactor pressure vessel integrity under hypothetical core melt down accident[J]. Nuclear techniques, 2013, 36(4): 040615
YAO Yangui NING Dong WU Zhiwei CAO Ming XIE Yongcheng HE Yinbiao YAO Weida. Research progress and recommendations on reactor pressure vessel integrity under hypothetical core melt down accident[J]. Nuclear techniques, 2013, 36(4): 040615 DOI: 10.11889/j.0253-3219.2013.hjs.36.040615.
Research progress and recommendations on reactor pressure vessel integrity under hypothetical core melt down accident
Background: It is very important to ensure the integrity of the reactor pressure vessel under core melt down accident.The high-temperature creep failure is the main failure mode of the reactor pressure vessel under core melt down accident.Purpose: This paper is to present an overview of research status and progress on high-temperature creep behavior of reactor pressure vessel considering the hypothetical core melt down scenario.Methods: Emphasis is placed on accomplished achievements in creep tests
scale model experiments and numerical simulation
and the domestic newly research productions on high-temperature creep behavior of reactor pressure vessel structure integrity.Conclusions: This paper also discusses the limitations of existing researches and indicates future research directions
such as multi-axis tensile tests
analysis of three-dimensional coupling temperature field
Benefit for the analysis of P-T limit curve of a home-made RPV using RTT0 instead of RTNDT
Stress analysis and assessment of RPV core support pads and surround bottom head
Sealing behavior simulation technology research for CPR1000 reactor pressure vessel
Research on structural integral assessment of cylinders with circumference cracks under pressurized thermal shock based on probabilistic fracture mechanics
Fatigue status assessment for reactor pressure vessel based on actual operational transient
Related Author
HE Yinbiao
HUI Hu
LI Hui
XUAN Fuzhen
CAO Yupeng
陶宏新
沈睿
曹明
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
Shanghai Nuclear Engineering Research & Design Institute
China Nuclear Power Design Company,Ltd.
Institute of Process Equipment & Control Engineering,Zhejiang University of Technology