Maximum cladding temperature prediction for nuclear research reactor WWR-SM Tashkent using best estimate code RELAP5/MOD3.3

The study aimed to evaluate the influence of different correlations implemented in the program on the prediction of the maximum surface temperature of the fuel bundle in a reactivity insertion accident when the reactor is at 11 MW critically. The calculation results were compared with the reference data and simultaneously shown for comparision.
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Maximum cladding temperature prediction for nuclear research reactor WWR-SM Tashkent using best estimate code RELAP5/MOD3.3