Nuclear power plant safety analyses

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

(.), Applications of Probabilistic Safety Assessment (PSA) for Nuclear Power Plants, IAEA TECDOC Series No. 1200, 2001.,
(.), Accident Analysis for Nuclear Power Plants, Safety Reports Series No. 23, IAEA, 2002.,
(.), D. Feretić, N. Čavlina, N. Debrecin, Nuklearne elektrane, Školska knjiga, Zagreb, 1995.,

General

ID 154778
  Winter semester
6 ECTS