PristupačnostNuclear power plant safety analyses
Data is displayed for the academic year: 2024./2025.
Lecturers
Course Description
Postulated initiating events (internal, external), Probabilistic analyses (fault tree, event tree, Level 1-3), Deterministic analyses, Accident and transient analyses using system codes (RELAP5), Subchannel core calculation (COBRA), Core safety limits, Fuel rod thermal and mechanical calculation (FRAPCON), Calculation of RIAs with spatial dependence (PARCS), Calculation of NPP containment (GOTHIC), Consequence analysis for radioactive effluents release and risk for the environment (COSYMA).
Study Programmes
Postgraduate doctoral study programme
Literature
(2001.), Applications of Probabilistic Safety Assessment (PSA) for Nuclear Power Plants, IAEA TECDOC Series No. 1200, International Atomic Energy Agency (IAEA)
(2002.), Accident Analysis for Nuclear Power Plants, Safety Reports Series No. 23, International Atomic Energy Agency (IAEA)
Danilo Feretić, Nikola Čavlina, Nenad Debrecin (1995.), Nuklearne elektrane, Školska knjiga, Zagreb
General
ID 154778
Winter semester
6 ECTS
L0 English Level