Abstract:A thermal-hydraulic analysis of a nuclear fuel rod subassembly of a Pressurized Water Reactor (PWR) has been performed during a Loss of Flow Accident (LOFA). Two different cladding materials are studied in this exercise namely, (a) conventional Zircaloy (Zr) and (b) a Silicon Carbide (SiC) cladding concept approach using monolithic SiC and SiC composite two-layer structure. The simulation is carried out by using USNRC licensed and AERB approved RELAP5/MOD3.4 code. A short-time problem is analyzed, neglecting t… Show more
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