Analysis of RELAP/SCDAPSIM/MOD3.2 Computer Code using QUENCH Experiments
- Brazilian Navy Technological Center, R. Professor Lineu Prestes, 2468, Sao Paulo, SP (Brazil)
- Innovative Space Power and Propulsion Institute, 2800 SW Archer Rd. Bldg, 554, P.O. Box 116502, University of Florida, Gainesville, FL, 32611-6502 (United States)
The experiments QUENCH-01/06 were modelled using RELAP5/SCDAPSIM MOD3.2(bd) computer code. The results obtained from these models were compared to the experimental data to evaluate the code performance. The experiments were performed in the Forschungszentrum Karlsruhe (FZK), Germany. The objective of the experimental program was the investigation of the core behaviour during a severe accident, focusing on rod claddings overheat due to zirconium oxidation at high temperatures and due to the strong thermal gradient developed when the nuclear reactor core is flooded as part of an accident management measure. Temperatures histories and hydrogen production were compared. Molecular hydrogen is a product of the oxidation reaction, serving as a parameter to measure the oxidation reaction. After some model adjustments, good predictions were possible. The temperatures and the hydrogen production parameters stayed, most of the transient time, inside the uncertainty envelop. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 21160798
- Country of Publication:
- United States
- Language:
- English
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