{"title":"HTR-PM反应堆保护系统可靠性分析","authors":"Shuqiao Zhou, Chao Guo, Duo Li","doi":"10.1109/ICRMS.2016.8050116","DOIUrl":null,"url":null,"abstract":"A high-temperature gas-cooled reactor-pebble bed module (HTR-PM), as a demonstration nuclear power plant (NPP), is now under construction in the Shandong province of China. The reactor protection system (RPS) in an HTR-PM is a safety-related system and is mainly in charge of monitoring safety-related parameters according to the reactor protection requirements. Thus, an RPS is very important to operations during the entire life cycle of an NPP. An RPS for an HTR-PM is completely designed and developed in China, which owns all intellectual property rights. Traditionally, the reliability of an RPS is evaluated based on a failure mode, effects, and criticality analysis (FMECA) and a fault tree analysis (FTA), which are static methods and cannot reflect the reliability of the system's dynamics. In this paper, we propose a dynamic reliability model for the RPS in an HTR-PM based on the Markov chain theory. Using this model, all states and their dynamic transition processes, especially the degradation process from a 2-out-of-4 structure to a 2-out-of-3 structure, are all determined. Moreover, based on this proposed model, an optimal surveillance test interval can be determined.","PeriodicalId":347031,"journal":{"name":"2016 11th International Conference on Reliability, Maintainability and Safety (ICRMS)","volume":"41 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2016-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"3","resultStr":"{\"title\":\"Reliability analysis for the reactor protection system of HTR-PM\",\"authors\":\"Shuqiao Zhou, Chao Guo, Duo Li\",\"doi\":\"10.1109/ICRMS.2016.8050116\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"A high-temperature gas-cooled reactor-pebble bed module (HTR-PM), as a demonstration nuclear power plant (NPP), is now under construction in the Shandong province of China. The reactor protection system (RPS) in an HTR-PM is a safety-related system and is mainly in charge of monitoring safety-related parameters according to the reactor protection requirements. Thus, an RPS is very important to operations during the entire life cycle of an NPP. An RPS for an HTR-PM is completely designed and developed in China, which owns all intellectual property rights. Traditionally, the reliability of an RPS is evaluated based on a failure mode, effects, and criticality analysis (FMECA) and a fault tree analysis (FTA), which are static methods and cannot reflect the reliability of the system's dynamics. In this paper, we propose a dynamic reliability model for the RPS in an HTR-PM based on the Markov chain theory. Using this model, all states and their dynamic transition processes, especially the degradation process from a 2-out-of-4 structure to a 2-out-of-3 structure, are all determined. Moreover, based on this proposed model, an optimal surveillance test interval can be determined.\",\"PeriodicalId\":347031,\"journal\":{\"name\":\"2016 11th International Conference on Reliability, Maintainability and Safety (ICRMS)\",\"volume\":\"41 1\",\"pages\":\"0\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2016-10-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"3\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"2016 11th International Conference on Reliability, Maintainability and Safety (ICRMS)\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.1109/ICRMS.2016.8050116\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"2016 11th International Conference on Reliability, Maintainability and Safety (ICRMS)","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/ICRMS.2016.8050116","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Reliability analysis for the reactor protection system of HTR-PM
A high-temperature gas-cooled reactor-pebble bed module (HTR-PM), as a demonstration nuclear power plant (NPP), is now under construction in the Shandong province of China. The reactor protection system (RPS) in an HTR-PM is a safety-related system and is mainly in charge of monitoring safety-related parameters according to the reactor protection requirements. Thus, an RPS is very important to operations during the entire life cycle of an NPP. An RPS for an HTR-PM is completely designed and developed in China, which owns all intellectual property rights. Traditionally, the reliability of an RPS is evaluated based on a failure mode, effects, and criticality analysis (FMECA) and a fault tree analysis (FTA), which are static methods and cannot reflect the reliability of the system's dynamics. In this paper, we propose a dynamic reliability model for the RPS in an HTR-PM based on the Markov chain theory. Using this model, all states and their dynamic transition processes, especially the degradation process from a 2-out-of-4 structure to a 2-out-of-3 structure, are all determined. Moreover, based on this proposed model, an optimal surveillance test interval can be determined.