Coupling between neutronic and thermalhydraulic codes

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Discussion Overview

The discussion revolves around the coupling of neutronic codes (WIMS & CITATION) with a thermalhydraulic code (COBRA) for applications in light water reactors (LWR), specifically for steady-state calculations. Participants seek resources, papers, and advice on this integration process.

Discussion Character

  • Exploratory
  • Technical explanation
  • Homework-related

Main Points Raised

  • One participant inquires about resources or tips for coupling WIMS & CITATION with COBRA.
  • Another participant expresses skepticism about the availability of references and notes that various groups are attempting to couple nuclear and thermalhydraulic codes, albeit perhaps in a crude manner.
  • Questions are raised regarding the specific type of LWR system (PWR or BWR) and whether the codes will be used for steady-state or transient simulations.
  • A participant confirms the use of the codes for a PWR and specifies that they will be used for steady-state calculations.
  • One participant offers to share a presentation on coupling neutronic and thermalhydraulic codes but lacks the recipient's email address.
  • Links to resources related to the Consortium for Advanced Simulation of Light Water Reactors (CASL) and a publication on thermal hydraulics modeling in nuclear power plants are provided, noting that while one resource pertains to VVER fuel, the principles are applicable.
  • A participant references a reply they posted in another thread that may also be helpful.

Areas of Agreement / Disagreement

Participants express uncertainty about the availability of references and the methods of coupling codes, indicating that multiple competing views and approaches may exist. The discussion remains unresolved regarding specific methodologies and resources.

Contextual Notes

Participants have not provided detailed assumptions or definitions regarding the coupling process, and there are unresolved questions about the applicability of shared resources to the specific context of PWR steady-state calculations.

Who May Find This Useful

Individuals interested in the integration of neutronic and thermalhydraulic codes, particularly in the context of light water reactors and steady-state simulations, may find this discussion relevant.

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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