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Simulation of post-LOCA heat transfer in nuclear fuel bundle
Mohamed Hisham Ibrahim Hussein, Boštjan Končar, Juhani Hyvärinen, Milan Tesinsky
Magistrsko delo
Oznake: nuclear engineering;light water reactors;nuclear fuel;thermal hydraulics;Loss of Coolant Accident;safety analysis;
Thermal hydraulic analysis is essential for ensuring safety in the nuclear industry, requiring reliable codes to predict reactor core behavior under both normal and accident conditions. This thesis examines the sub-channel code Coolant-boiling in Rod Arrays- Two Fluids (CTF), to simulate the top re ...
Leto: 2024 Vir: Fakulteta za matematiko in fiziko (UL FMF)
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