基于塑性极限载荷的奥氏体不锈钢钢承压管道役致裂纹接受标准研究  

STUDY ON ACCEPTANCE CRITERIA OF SERVICE INDUCED CRACKS FOR AUSTENITIC STAINLESS STEEL PIPING BASED ON PLASTIC LIMIT LOAD CRITERIA

作　　者：陈明亚[1,2] 向文欣 祁爽 马若群 宁方卯 王永刚 邵春兵 师金华 彭群家 张国栋 CHEN MingYa;XIANG WenXin;QI Shuang;MA RuoQun;NING FangMao;WANG YongGang;SAO ChunBin;SHI JinHua;PENG QunJia;ZHANG GuoDong(Suzhou Nuclear Power Research Institute,Suzhou 215004,China;Shandong University,Jinan 250100,China;Taishan Nuclear Power Joint Venture Co.,Ltd.,Taishan 529200,China;Nuclear and Radiation Safety Centre.MEE,Beijing 100082,China)

机构地区：[1]苏州热工研究院,苏州215004 [2]山东大学,济南250100 [3]台山核电合营有限责任公司,台山529200 [4]生态环境部核与辐射安全中心,北京100082

出　　处：《机械强度》2023年第2期469-473,共5页Journal of Mechanical Strength

基　　金：国家重点研发计划(2020YFB1901500);国家自然科学基金项目(12075274)资助。

摘　　要：为保证核电厂长期安全、高效运行,需制订一回路承压边界管道役致裂纹的接受标准,以满足工程上的快速评估需要。对于含裂纹的承压管道,通常需要进行复杂的断裂评价和极限载荷分析。通过数值仿真分析,论证了对于断裂韧性较好的奥氏体不锈钢结构,采用塑性极限载荷作为结构临界状态的合理性,并基于结构设计塑性极限载荷不降低的准则,制订了奥氏体不锈钢管道役致裂纹的接受标准。研究表明,确定的一回路奥氏体不锈钢承压直管段的役致裂纹接受尺寸与美国ASME规范提供数据接近,但明显高于法国RSE-M规范相关数据,法国RSE-M提供的数据过于保守。In order to ensure safety and efficient state of nuclear power plant in the long time operation,it is necessary to figure out the acceptance table of defects of the primary loop to meet the requirement of rapid assessment in engineering.It is necessary to do the fracture mechanics and plastic limit load analysis for the cracked pipe.Through numerical simulation analysis,the rationality of adopting plastic limit load as the critical state of austenitic stainless steel structure with good fracture toughness is demonstrated.Based on the criterion of non-decreasing the plastic limit load in design state,the acceptance standard of defects for the austenitic stainless steel pipe is established in this paper.The results show that the defect acceptance size of the primary circuit pipe is close to that in the ASME code,but much larger than that of the RSE-M code,and the RSE-M code is too conservative.

关 键 词：承压管道 奥氏体不锈钢管 极限载荷 役致裂纹 接受标准 

分 类 号：TL351.6[核科学技术—核技术及应用]