华龙一号反应堆冷却剂系统抗震设计关键技术

熊夫睿; 沈平川; 王新军; 叶献辉; 张毅雄

doi:10.7538/yzk.2021.youxian.0959

华龙一号反应堆冷却剂系统抗震设计关键技术

中国核动力研究设计院核反应堆系统设计技术重点实验室,四川成都610213

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出版历程
- 刊出日期: 2022-06-19

Key Technology of HPR1000 Reactor Coolant System Seismic Resistance Design

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China

摘要

摘要: 华龙一号是满足三代核电技术指标要求的自主化百万千瓦压水堆核电机组，其抗震能力达到0.3g。为达到该抗震指标，对反应堆冷却剂系统在关键设备结构加强及优化、管道破前漏技术应用、抗震载荷分配精细化计算、抗震设计标准化、抗震裕度评价等方面开展了关键技术研究，建立了一套抗震能力提升的策略，完成了华龙一号反应堆冷却剂系统抗震优化和评估工作。相关技术已在华龙批量生产堆型中得以应用。
- 华龙一号 ,
- 反应堆冷却剂系统 ,
- 抗震分析 ,
- 载荷环境
Abstract: HPR1000 (Hualong No.1) was developed upon over 30 years of pressurized water reactor (PWR) R&D experience of CNNC. It has fully absorbed the advanced design philosophy of GENⅢ nuclear power and the overall engineering experiences including design, construction, testing and operating among China’s current PWR fleet. HPR1000 satisfies the 1 000 MWe power level GENⅢ technical specifications with the 0.3g seismic resistance capability. In order to reach this capability, several key technologies were developed including structural reinforcement of key equipment, leakbeforebreak (LBB) application on piping, refined calculation of reactor coolant system (RCS) load distribution, standard seismic resistance design practice and safety margin evaluation. Upon these technologies, a set of seismic resistance improvement strategy was devised that guides the accomplishment of RCS seismic resistance evaluation and optimization. The technologies reported in this paper are applied in successive Hualong projects. Short descriptions of abovementioned key technologies that leads to successful seismic resistance design are presented herein: 1) Structural reinforcement are adopted at key locations to enable improved functional requirement, such as the enlarged nozzle diameter and wall thickness of reactor pressure vessel, and such improvement also facilitates stronger structural integrity upon resisting dynamical loadings; 2) The utilization of LBB technology on RCS main pipe and the surge pipe alleviates the load considerations under the loss of coolant accident (LOCA), which is usually considered in conjunction with safe shutdown earthquake (SSE) load for GENⅡ nuclear power plant RCS structural analyses, and the introduction of LBB thus greatly reduces the conservatism on RCS mechanical analysis; 3) The load distribution modeling and computation. Multifidelity load calculation modeling strategy is adopted in this study to enable the capture of main dynamical responses at different resolutions. Interfacial loading data are exchanged across each level for quick iterations of structural design and optimization; 4) Standardization of seismic environment. This is achieved via comparative study of seismic response spectrum among a set of representative rock conditions. Envelop spectrum is proposed herein with adequate conservatism that will be used for future plant design; 5) Safety margin analysis (SMA). The essence of SMA is to estimate the potential of seismic resistance on key components in RCS. SMA is a key part of plant probability safety analysis (PSA) procedure. High confidence low probability failure (HCLPF) is used to quantify how much margin a component may have. Such information is helpful on learning the overall capability of resisting earthquake of the entire RCS. Moreover, SMA results reveal the vulnerability of RCS components.
- HPR1000 ,
- reactor coolant system ,
- anti-seismic analysis ,
- load environment

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参考文献(11)

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