Research and Design of Diversity Protection System for Small Modular Reactor
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摘要: 对模块式小型堆多样性保护系统（RDA）的关键技术进行了研究和分析论证，首次采用基于概率论与确定论相结合的多样性保护信号设计方法，对保护信号整定值及延迟时间的确定进行了深入研究，实现了保护信号设置最小化和保护功能最大化；同时在RDA设计中全面应用多样性和独立性设计技术，构建了高可靠、低误动率的系统架构，显著提升了模块式小型堆的安全性和经济性，满足核电厂纵深防御和多样性要求，相关技术指标已达到了国际先进水平。
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关键词:
- 模块式小型堆 /
- 多样性保护系统（RDA） /
- 软件共因故障（SWCCF） /
- 纵深防御 /
- 系统设计
Abstract: According to the characteristics of small modular reactor, the key technologies of diversity protection system (RDA) are studied and analyzed. The design method of diversity protection signal based on the combination of probability theory and certainty theory is adopted for the first time, and the determination of protection signal setting value and delay time is deeply studied, which realizes the minimization of protection signal setting and the maximization of protection function; At the same time, with the comprehensive application of diversity and independent design technology in RDA design, a system architecture with high reliability and low misoperation rate is constructed, which significantly improves the safety and economy of small modular reactor, meets the requirements of defense in depth and diversity of nuclear power plant, and the relevant technical indicators have reached the international advanced level. -
表 1 RDA系统保护信号方案
Table 1. RDA System Protection Signal Scheme
停堆/专设功能 保护信号 反应堆紧急停堆 功率量程中子注量率高（高定值） 稳压器压力高1 稳压器压力低1 手动触发 汽轮机停机 反应堆紧急停堆 手动触发 非能动余热排出系统启动 反应堆紧急停堆 手动触发 堆芯补水箱注入 稳压器压力低2 反应堆出口温度高 手动触发 反应堆冷却剂泵停运 堆芯补水箱注入 手动触发 安全壳隔离 操作大厅温度高 手动触发 主给水隔离 反应堆紧急停堆 手动触发 内置换料水箱注入 手动触发 安全壳再循环驱动 手动触发 自动卸压第1、2、3级驱动 手动触发 
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[1] PRECKSHOT G G. Method for performing diversity and defense-in-depth analyses of reactor protection systems: NUREG/CR-6303[R]. Washington, DC: U. S. Nuclear Regulatory Commission, 1994: 2-12. [2] 周继翔,朱攀,肖鹏. 核电厂仪控系统纵深防御和多样性设计[J]. 核动力工程,2014, 35(1): 122-124. [3] U. S. Nuclear Regulatory Commission. Guidance for evaluation of diversity and defense-in-depth in digital computer-based instrumentation and control systems: NUREG-0800 BTP 7-19[S]. Washington, DC: U. S. Nuclear Regulatory Commission, 2016: 5-19. [4] U. S. Nuclear Regulatory Commission. Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants: 10 CFR Part 50.62[S]. Washington, DC: Government Publishing Office, 2020: 960-961. -
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