Browsing by Subject "Reactors nuclears"
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Benchmarking Study of Asyst Code Against Cora-18 Bwr Experiment with Integrated Uncertainty Analysis
(2025)Verifying and validating thermohydraulic codes for severe accidents in nuclear reactors is an ongoing process that requires a combination of experimental data, benchmarking, uncertainty analysis, and ... -
Comparison of the QUENCH-06 experiment between ASYST and RELAP/SCDAPSIM 3.4
(2024)The behavior of nuclear reactors during a severe accident is significantly affected by hydrogen generation. The QUENCH experiments are crucial for understanding the behavior of nuclear reactors during ...