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作 者:王勇[1] 关银柏 张彦召[1] 郭峰 李玲[1] 郑斌贤 卢国鹏 Wang Yong;Guan Yinbo;Zhang Yanzhao;Guo Feng;Li Ling;Zheng Binxian;Lu Guopeng(Suzhou Nuclear Power Research Institute Co.,ltd.Suzhou 215000,China;Taishan Nuclear Power Joint Venture Co.,ltd.Jiangmen 529200,China)
机构地区:[1]苏州热工研究院有限公司,苏州215000 [2]台山核电合营有限公司,江门529200
出 处:《核安全》2025年第1期86-91,共6页Nuclear Safety
摘 要:堆内构件是EPR机组重要的机械设备,随着服役时间的延长,由于长期受到高中子辐照的影响,以及考虑到其特殊的结构特点、复杂的拉应力以及反应堆冷却剂环境等因素,中子辐照脆化、辐照促进应力腐蚀开裂(IASCC)、磨损等老化问题会逐步显现。借鉴国内外堆内构件老化研究和管理实践,本文以EPR机组堆内构件主要部件为分析对象,开展老化筛选、FMECA评价和分类管理,制定适用于EPR机组堆内构件的老化管理大纲和策略,为国内外EPR机组堆内构件的安全可靠运行提供指导和依据。Reactor Vessel Internal(RVI)is a mechanical equipment important for safety in EPR units.With the extension of service time,ageing issues such as neutron irradiation embrittlement,irradiation-assisted stress corrosion cracking(IASCC),and wear will gradually emerge due to long-term exposure to high neutron irradiation,along with the considerations of their unique structural characteristics,complex tensile stresses,and the reactor coolant environment.Drawing on domestic and international ageing research and management practices on RVI component,this analysis focuses on the main components of the EPR unit internals.It carries out ageing screening,FMECA evaluation,and classification management to develop an ageing management programme and strategy for the internal components of EPR units.This provides guidance and a basis for the safe and reliable operation of internal components in EPR units both domestically and internationally.
分 类 号:TL34[核科学技术—核技术及应用]
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