{"title":"核电厂堆芯保护计算器可靠性分析","authors":"Y. Lukic","doi":"10.1109/RAMS.1996.500651","DOIUrl":null,"url":null,"abstract":"This paper describes a study performed in support of the decision-making process regarding possible replacement/upgrade of the core protection calculator system (CPCS) at the Pale Verde nuclear generating station. Here, the authors present the methodology and results of a CPCS reliability study performed to: (a) calculate the frequency of CPCS hardware failure induced spurious reactor trips; (b) provide a qualitative basis for assessing whether the current reliability may be reasonably expected to be maintained during the forty year design life of the system; and (c) provide recommendations to help maintain system reliability into the future.","PeriodicalId":393833,"journal":{"name":"Proceedings of 1996 Annual Reliability and Maintainability Symposium","volume":null,"pages":null},"PeriodicalIF":0.0000,"publicationDate":"1996-01-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"2","resultStr":"{\"title\":\"Nuclear power plant core-protection-calculator reliability analysis\",\"authors\":\"Y. Lukic\",\"doi\":\"10.1109/RAMS.1996.500651\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"This paper describes a study performed in support of the decision-making process regarding possible replacement/upgrade of the core protection calculator system (CPCS) at the Pale Verde nuclear generating station. Here, the authors present the methodology and results of a CPCS reliability study performed to: (a) calculate the frequency of CPCS hardware failure induced spurious reactor trips; (b) provide a qualitative basis for assessing whether the current reliability may be reasonably expected to be maintained during the forty year design life of the system; and (c) provide recommendations to help maintain system reliability into the future.\",\"PeriodicalId\":393833,\"journal\":{\"name\":\"Proceedings of 1996 Annual Reliability and Maintainability Symposium\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1996-01-22\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"2\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Proceedings of 1996 Annual Reliability and Maintainability Symposium\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.1109/RAMS.1996.500651\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Proceedings of 1996 Annual Reliability and Maintainability Symposium","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/RAMS.1996.500651","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Nuclear power plant core-protection-calculator reliability analysis
This paper describes a study performed in support of the decision-making process regarding possible replacement/upgrade of the core protection calculator system (CPCS) at the Pale Verde nuclear generating station. Here, the authors present the methodology and results of a CPCS reliability study performed to: (a) calculate the frequency of CPCS hardware failure induced spurious reactor trips; (b) provide a qualitative basis for assessing whether the current reliability may be reasonably expected to be maintained during the forty year design life of the system; and (c) provide recommendations to help maintain system reliability into the future.