SUMMARY
The discussion focuses on coupling the neutronic codes WIMS and CITATION with the thermalhydraulic code COBRA for use in Pressurized Water Reactor (PWR) systems. Participants emphasize the lack of comprehensive resources on this topic, although they acknowledge that various groups are exploring similar coupling methods. The codes are intended for steady-state calculations, and references to the Consortium for Advanced Simulation of Light Water Reactors (CASL) and relevant publications are provided to assist in this endeavor.
PREREQUISITES
- Understanding of neutronic codes, specifically WIMS and CITATION
- Familiarity with thermalhydraulic codes, particularly COBRA
- Knowledge of Pressurized Water Reactor (PWR) systems
- Experience with steady-state simulation techniques
NEXT STEPS
- Research the CASL initiative for advanced simulation techniques in light water reactors
- Explore the principles of thermal hydraulics modeling in nuclear power plants
- Investigate existing literature on coupling neutronic and thermalhydraulic codes
- Review case studies involving VVER fuel and its application in similar coupling scenarios
USEFUL FOR
Nuclear engineers, researchers in reactor physics, and professionals involved in thermalhydraulic modeling for nuclear power plants will benefit from this discussion.