Assessment of RELAP5-3D for Analysis of Very High Temperature Gas-Cooled Reactors

Conference · Sat Oct 01 00:00:00 EDT 2005

DOI:https://doi.org/10.2172/911255· OSTI ID:911735

Oh, Chang; Siefken, Larry; Davis, Cliff

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

Related Subjects

99 - GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
AIR
COMPUTER CODES
DATA
DIFFUSION
LOSS OF COOLANT
NATURAL CONVECTION
REACTORS
THERMAL HYDRAULICS
air ingress
chemical diffusion
gas-cooled reactor
high temperature
natural circulation
RELAP5-3D