Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment

To ensure the applicability of accident-tolerant fuels, their behaviors under various accidental conditions must be assessed. While dependences behavior single physical parameters can investigated in single- or separate-effect experiments, and more complex phenomena using integral-effect tests, an entire system as a nuclear power plant core computer code modeling. One most commonly used codes for assessment severe accidents is MELCOR 2.2. In version 18019, authors enabled modeling fuel with FeCrAl cladding (namely, alloy B136Y3) first time, GOX model. The ability this model to reasonably accurately predict accident quenching was verified work by QUENCH-19 experiment carried out Karlsruhe Institute Technology on QUENCH experimental device subsequent comparison calculation results experiment. This article proves that evaluate considered conservative.