{"title":"Simulation Research on Safe Load-Reducing Operation Margin of Nuclear Power Unit With Clogging of the CFI Drum Net","authors":"Jinchao Liu, Yaozu Lin, Bijun Chen, Xue Lyu, Jiayi Li, Heng Zhang","doi":"10.1115/icone29-92540","DOIUrl":null,"url":null,"abstract":"\n As the final heat sink of the nuclear power plant, the cool source is responsible for the safety function of the waste heat export of the reactor. The explosive invasion of marine organisms and other wastes have a great impact on the cold source system of nuclear power plants, which will lead to transient events, load reduction and shutdown of nuclear power unit, and even affect the availability of the cold source system in severe cases. which are huge threats and challenges for the safe and stable operation of unit. thereby reducing the power generation efficiency, safety, economy, and sustainable development of nuclear power plants. Clogging of the CFI drum net is one of the important factors causing cold source system accidents. this paper puts forward the solution idea of maintaining the water level of the forebay through the variable frequency pump, so as to ensure that the CRF pump keeps running state under the condition of cold source blockage, so as to maintain the function of the cold source system. and based on the full range simulator of nuclear power units, consider CFI drum network differential pressure high alarm failure combined with a monitoring device for the blockage degree of the drum net, the scheme is simulated and verified, and the load that the nuclear power unit can operate safely under different blocking degrees of drum network is given. the research results of this paper provide a solution for alleviating the cold source problem, and the solution can also provide a reference for the safety improvement of the cold source of actual unit and the design of new reactor.","PeriodicalId":365848,"journal":{"name":"Volume 5: Nuclear Safety, Security, and Cyber Security","volume":"24 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Volume 5: Nuclear Safety, Security, and Cyber Security","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1115/icone29-92540","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0
Abstract
As the final heat sink of the nuclear power plant, the cool source is responsible for the safety function of the waste heat export of the reactor. The explosive invasion of marine organisms and other wastes have a great impact on the cold source system of nuclear power plants, which will lead to transient events, load reduction and shutdown of nuclear power unit, and even affect the availability of the cold source system in severe cases. which are huge threats and challenges for the safe and stable operation of unit. thereby reducing the power generation efficiency, safety, economy, and sustainable development of nuclear power plants. Clogging of the CFI drum net is one of the important factors causing cold source system accidents. this paper puts forward the solution idea of maintaining the water level of the forebay through the variable frequency pump, so as to ensure that the CRF pump keeps running state under the condition of cold source blockage, so as to maintain the function of the cold source system. and based on the full range simulator of nuclear power units, consider CFI drum network differential pressure high alarm failure combined with a monitoring device for the blockage degree of the drum net, the scheme is simulated and verified, and the load that the nuclear power unit can operate safely under different blocking degrees of drum network is given. the research results of this paper provide a solution for alleviating the cold source problem, and the solution can also provide a reference for the safety improvement of the cold source of actual unit and the design of new reactor.