{"title":"旁通对VVER440燃料组件热工水力学的影响","authors":"J. Jakubec, Juraj Paulech, V. Kutǐs, G. Galik","doi":"10.1515/scjme-2017-0007","DOIUrl":null,"url":null,"abstract":"Abstract The paper deals with CFD modelling and simulation of coolant flow within the nuclear reactor VVER 440 fuel assembly. The influence of coolant flow in bypass on the temperature distribution at the outlet of the fuel assembly and pressure drop was investigated. Only steady-state analyses were performed. Boundary conditions are based on operating conditions. ANSYS CFX is chosen as the main CFD software tool, where all analyses are performed.","PeriodicalId":35968,"journal":{"name":"Strojnicky Casopis","volume":"67 1","pages":"69 - 76"},"PeriodicalIF":0.0000,"publicationDate":"2017-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1515/scjme-2017-0007","citationCount":"1","resultStr":"{\"title\":\"Influence of Bypass on Thermo-Hydraulics of VVER 440 Fuel Assembly\",\"authors\":\"J. Jakubec, Juraj Paulech, V. Kutǐs, G. Galik\",\"doi\":\"10.1515/scjme-2017-0007\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Abstract The paper deals with CFD modelling and simulation of coolant flow within the nuclear reactor VVER 440 fuel assembly. The influence of coolant flow in bypass on the temperature distribution at the outlet of the fuel assembly and pressure drop was investigated. Only steady-state analyses were performed. Boundary conditions are based on operating conditions. ANSYS CFX is chosen as the main CFD software tool, where all analyses are performed.\",\"PeriodicalId\":35968,\"journal\":{\"name\":\"Strojnicky Casopis\",\"volume\":\"67 1\",\"pages\":\"69 - 76\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2017-04-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"https://sci-hub-pdf.com/10.1515/scjme-2017-0007\",\"citationCount\":\"1\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Strojnicky Casopis\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.1515/scjme-2017-0007\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q3\",\"JCRName\":\"Engineering\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Strojnicky Casopis","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1515/scjme-2017-0007","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"Engineering","Score":null,"Total":0}
Influence of Bypass on Thermo-Hydraulics of VVER 440 Fuel Assembly
Abstract The paper deals with CFD modelling and simulation of coolant flow within the nuclear reactor VVER 440 fuel assembly. The influence of coolant flow in bypass on the temperature distribution at the outlet of the fuel assembly and pressure drop was investigated. Only steady-state analyses were performed. Boundary conditions are based on operating conditions. ANSYS CFX is chosen as the main CFD software tool, where all analyses are performed.
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