Browsing by Author "Ergün, Ş."

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    Making Safety Analysis of PWR Pressure Vessel with Favor Code
    (Ankara Üniversitesi Nükleer Bilimler Enstitüsü, 2018) Yıldırım, A.; Ergün, Ş.; Other; Other
    Reactor 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.