Making Safety Analysis of PWR Pressure Vessel with Favor Code

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dc.contributor.authorYıldırım, A.
dc.contributor.authorErgün, Ş.
dc.contributor.departmentOthertr_TR
dc.contributor.facultyOthertr_TR
dc.date.accessioned2022-01-24T14:56:47Z
dc.date.available2022-01-24T14:56:47Z
dc.date.issued2018
dc.description.abstractReactor Pressure Vessels are the most important structures in view of keeping the integrity for nuclear power plants. Fracture Analysis of Vessels Oak Ridge (FAVOR) is a code which is used in USA for PWRs and BWRs to make probabilistic analysis to calculate both Pressure Vessel Crack Initiation Frequency and Pressure Vessel Failure Frequency, using thermal hydraulic data, material properties, flaw properties of pressure vessels for some kind of accidents and start up-close down situations. The analysis is concentrated on the belt line of the pressure vessels; this region is the most vulnerable region of the vessels because of the fast neutron fluence, and so material embrittlement increases and fracture toughness decreases in this region. In this study the flaw data files which were supplied have been changed by decreasing the density of flaws which have different sizes and the Crack Initiation Frequency and Failure Frequency of reactor vessels have been searched. Consequently it has been seen that these frequencies have lower values.tr_TR
dc.description.indexYoktr_TR
dc.identifier.issue01tr_TR
dc.identifier.startpage6tr_TR
dc.identifier.urihttp://hdl.handle.net/20.500.12575/77216
dc.identifier.volume05tr_TR
dc.language.isoentr_TR
dc.publisherAnkara Üniversitesi Nükleer Bilimler Enstitüsütr_TR
dc.relation.journalJournal of Nuclear Sciencestr_TR
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Başka Kurum Yazarıtr_TR
dc.subjectPWRtr_TR
dc.subjectPressure Vesseltr_TR
dc.subjectFAVOR Codetr_TR
dc.titleMaking Safety Analysis of PWR Pressure Vessel with Favor Codetr_TR
dc.typeArticletr_TR

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Cilt:05 Sayı:01 (2018)