压力容器2025，Vol.42Issue(3)：62-70,9.DOI:10.3969/j.issn.1001-4837.2025.03.008
压水堆核电厂厚壁承压设备设计评价和在役评定分析探讨
Discussion on design evaluation and in-service assessment of thick-walled pressure equipment in PWR nuclear power plants
摘要
Abstract
Due to historical development and the control of design evaluation workload,significant differences exist in the evaluations of the design and in-service stages for thick-walled pressure equipment.In the open literature,there are numerous mix-ups of design evaluation and in-service assessment requirements.For example,the evaluation criterion of pre-service evaluation is widely used to evaluate the safety of defects found in the in-service inspection.Taking the development of the primary circuit temperature-pressure limit curve as an example,this paper introduces the differences between the simplified analysis in the design stage and the precise assessment in the in-service stage,focusing on reference defects,welding residual stress,material fracture toughness,and evaluation coefficients.The acceptable crack information and the shortcomings of the existing evaluation method are also discussed.Finally,the on-line structural integrity analysis system which can realize the accurate evaluation in in-service stage is introduced.关键词
承压设备/核压力容器/P-T曲线/设计评价/在役评定Key words
pressure equipment/nuclear pressure vessel/P-T curve/design evaluation/in-service evaluation分类
机械制造引用本文复制引用
陈明亚,曹昱澎,孙欣,余伟炜,彭群家,赵万祥..压水堆核电厂厚壁承压设备设计评价和在役评定分析探讨[J].压力容器,2025,42(3):62-70,9.基金项目
国家自然科学基金项目(U21B2076,U21132076) （U21B2076,U21132076）
