Nuclear Reactor Safety/Analys

Catalog description

Prerequisites: NE 2110. Nuclear plant systems in PWRs, BWRs, SFRs and GCRs; safety systems and emergency core cooling systems in PWRs, BWRs, PHWs & GCRs; nuclear reactor safeguard systems; defense-in-depth design; nuclear reactor accident scenarios; design-basis accidents (DBA) and beyond DBA; examples of major commercial reactor accidents (TMI-2, Chernobyl, Fukushima); indications of transients in operating reactors and emergency shutdown; regulatory issues related to reactor safety; study of reactor transients; elements of probabilistic risk assessment (PRA); thermal hydraulic and severe accident computer codes recommended by the NRC.