压水堆核电厂设备疲劳监测系统开发及关键技术研究

Development of the Fatigue Monitor and the Aging Management System for PWR NPPs and Research on Key Technology

2007年美国核管会(NRC)颁布的RG 1.207明确表示,新建核电厂需考虑轻水堆(LWR)一回路水环境对设备疲劳性能的影响,2018年NRC发布了1版的RG 1.207,不仅要求新建核电厂须考虑LWR水环境对疲劳性能的影响,在老电厂申请许可证延续时也须考虑LWR水环境对疲劳性能的影响,并在其技术支持报告NUREG/CR-6909中给出了环境疲劳修正因子(Fen)的评价方法。国家核安全局(NNSA)颁发建造许可证时提出的建造许可(CP)条件也要求在设计阶段考虑环境影响疲劳(EAF)问题。为了满足AP1000依托项目对疲劳监测系统的工程需要,本文在原有电厂承压设备疲劳寿命监测装置和波动管热分层温度测量技术的基础上提出了一种能够满足RG1.207导则的核电厂一回路设备及管道的疲劳监测方案,研制了具有完全自主知识产权的核电厂承压设备和管道集成化疲劳诊断和监测系统FAMOLES,并已应用于AP1000依托项目的三门1号机组及海阳1号和2号机组。

RG 1.207 issued by the US nuclear administration admission(NRC) in 2007 required that the effects of light water reactor(LWR) environments on fatigue behavior should be considered for newly-built power plants. Moreover, NRC updated RG 1.207 to revision 1 required that the environmentally assisted fatigue(EAF) problem should also be considered for license review and life extension application of old plants, an evaluation method of the environmental fatigue correction factor(Fen) considering the EAF problem is provided in the technology research report of NUREG/CR-6909. The National nuclear safety administration(NNSA) proposed a construction permission(CP) condition requiring that the EAF problem should be considered during the design phase. According to the demand of the AP1000 self-rely project, this paper proposed an plan of fatigue monitoring based on the fatigue monitoring system for the thermal power plant and the surge line thermal stratification measurement technology, which can satisfy the requirement of RG 1.207 and the developed fatigue monitoring system(FAMOLES) for the primary loop pressure retaining equipment and piping of PWR NPP, which has completely independent intellectual property. The fatigue monitoring system has been applied in the AP1000 self-rely project of Unit 1 of Sanmen NPP and Unit 1 & 2 of Haiyang NPP.