Browsing II. Eurasian conference nuclear science and its application : proceedings, 16-19 September, 2002. Almaty, Kazakhstan by Subject "Basınçlı kap bütünlüğü"
(National Nuclear Center of the Republic of Kazakhstan / Institute of Nuclear Physics, 2003) Özdere Gülol, Oya; Çolak, Üner; TAEK-NGD
In this study, nuclear reactor pressure vessel analysis is performed via deterministic and probabilistic methods for six different transient conditions which may cause pressurized thermal shock. A classical four loop PWR with SA533B type ferritic steel pressure vessel is analyzed. Deterministic analysis is performed for obtaining change in material properties and mechanical state of vessel against temperature and pressure changes. In probabilistic analysis, failure probabilities for vessel beltline region welds are calculated. VISA II computer code is employed for both deterministic and probabilistic analysis.