Coupling between neutronic and thermalhydraulic codes

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Coupling WIMS and CITATION as neutronic codes with COBRA for thermal-hydraulic analysis is being explored, particularly for Pressurized Water Reactor (PWR) systems focusing on steady-state calculations. There is a lack of specific references, but various groups are attempting to integrate nuclear and thermal-hydraulic codes, albeit in a rudimentary manner. Resources mentioned include a presentation on coupling these codes and information from the Consortium for Advanced Simulation of Light Water Reactors (CASL). The University of Tennessee is involved in related research, and a publication on thermal hydraulics modeling in nuclear power plants may provide useful insights. Overall, the integration of these codes aims to enhance simulation capabilities in nuclear reactor analysis.
libertad
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Hi there,
I'm going to couple WIMS & CITATION as neutronic codes with COBRA as an thermalhydraulic code.
Please let me know if there is any resources, papers or tips and tricks to do so.

Thanks
 
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I suspect there isn't any references. I do know that various groups are attempting to couple nuclear and T/H codes, and some perhaps have in a crude way.

Is this for an LWR system? PWR, BWR or both?

Will the code be used for steady-state or transient simulations?
 
Astronuc said:
I suspect there isn't any references. I do know that various groups are attempting to couple nuclear and T/H codes, and some perhaps have in a crude way.

Is this for an LWR system? PWR, BWR or both?

Will the code be used for steady-state or transient simulations?


I want to use it for a PWR and the codes are used for steady-state calculations.
 


Hi Libertad
I have a peresentation(ppt) about coupling neutronic & thrmohydrolic codes(wims+citation+cobra). But I have not your mail to sending you.
 
FYI - CASL - Consortium for Advanced Simulation of Light Water Reactors (CASL)

http://www.ornl.gov/ornlhome/b_roll/casl.shtml

University of Tennessee - Knoxville will likely have a role in this program.
 
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