Assessment of RELAP5-3D for Analysis of Very High Temperature Gas-Cooled Reactors
The RELAP5-3D© computer code is being improved for the analysis of very high temperature gas-cooled reactors. Diffusion and natural circulation can be important phenomena in gas-cooled reactors following a loss-of-coolant accident. Recent improvements to the code include the addition of models that simulate pressure loss across a pebble bed and molecular diffusion. These models were assessed using experimental data. The diffusion model was assessed using data from inverted U-tube experiments. The code’s capability to simulate natural circulation of air through a pebble bed was assessed using data from the NACOK facility. The calculated results were in reasonable agreement with the measured values.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- DOE - NE
- DOE Contract Number:
- DE-AC07-99ID-13727
- OSTI ID:
- 911735
- Report Number(s):
- INL/CON-05-00282; TRN: US200801%%185
- Resource Relation:
- Conference: The 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11),Avignon, France,10/02/2005,10/06/2005
- Country of Publication:
- United States
- Language:
- English
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