反应堆冷却剂泵保护系统可靠性分析

发布时间：2018-04-18 01:33

本文选题：二元决策图 + 故障树分析法　；参考：《上海交通大学》2013年硕士论文

【摘要】：反应堆保护系统是由安全级仪表与控制系统实现的，新一代核电仪控系统已经采用数字化技术。目前，我国核电站使用的数字化仪控系统均是由外国公司设计生产。核电数字化保护系统的自主开发对我国核电技术发展具有重要的意义。按照核电标准与导则的要求，只有通过验证与确认的产品才能应用于安全级仪控系统。目前国内尚未建立规范的验证与确认认证程序，在保护系统维护阶段的验证与确认程序主要是从功能上进行仿真测试。本文从核电数字化反应堆保护系统软件开发平台需求出发，考虑保护系统维护阶段的验证与确认活动与软件可靠性分析相结合，根据可靠性分析结果提出改进建议，为核电保护系统的改进与自主设计提供思路。本文的创新点包括以下三点： 1)提出将软件可靠性分析技术应用到核电厂安全级应用软件维护阶段的验证与确认活动中，从而提出保护系统的改进建议，用于满足不断升级的验证与确认标准、保证自主设计的数字化保护系统的质量； 2)结合工程实际分析核电数字化保护系统的故障模式，建立反应堆冷却剂泵保护逻辑的故障树结构与二元决策图，进行可靠性定性分析与定量计算； 3)根据可靠性分析结果提出两种反应堆保护系统的改进方法，将两种方法分别用于反应堆冷却剂泵保护逻辑并验证各自的改进效果，同时对两种改进结果进行比较；
[Abstract]:The reactor protection system is realized by the safety level instrument and control system. The new generation of nuclear power instrument control system has adopted digital technology.At present, the digital instrument control systems used in nuclear power plants in China are designed and produced by foreign companies.The independent development of digital nuclear power protection system is of great significance to the development of nuclear power technology in China.According to the requirements of nuclear power standards and guidelines, only through verification and validation of products can be applied to safety level meter control system.At present, no standard verification and verification program has been established in our country, and the verification and verification program in the protection system maintenance stage is mainly simulated and tested from the function.Based on the requirement of software development platform for digital reactor protection system of nuclear power, this paper considers the combination of verification and validation activities in the maintenance stage of the protection system and software reliability analysis, and puts forward some suggestions for improvement according to the results of reliability analysis.It provides ideas for the improvement and independent design of nuclear power protection system.The innovations of this paper include the following three points:1) the software reliability analysis technology is applied to the verification and validation of the safety level application software maintenance stage of the nuclear power plant, and some suggestions for the improvement of the protection system are put forward, which are used to meet the continuously upgraded verification and confirmation standards.Ensure the quality of the digital protection system designed by ourselves;2) the fault mode of digital protection system of nuclear power plant is analyzed based on engineering practice, fault tree structure and binary decision diagram of reactor coolant pump protection logic are established, and reliability qualitative analysis and quantitative calculation are carried out.3) according to the results of reliability analysis, two improved methods of reactor protection system are put forward. The two methods are applied to the protection logic of reactor coolant pump and their improvement results are verified. At the same time, the results of the two improvements are compared.
【学位授予单位】：上海交通大学
【学位级别】：硕士
【学位授予年份】：2013
【分类号】：TL364

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