This work presents a novel core multiphysics coupling method and its application to geometries and thermal hydraulic operating conditions typical of U.S. PWRs. Monte Carlo based radiation transport from the MCNP v6.1.0 package and finite volume thermal hydraulic (TH) packages provided by ANSYS-FLUENT v14.0 are combined to produce results with intra-pin resolved spatial resolution equivalent to state-of-the-art reactor physics and multi-physics suites. The Virtual Environment for Reactor Applications (VERA) whose development is spearheaded at Oak Ridge National Laboratory is one such example package. Results from the MCNP-FLUENT coupling framework are compared to a deterministic solution provided by the MPACT-COBRA-TF (MPACT-CTF) package available in VERA. Comparisons between the MCNP-FLUENT methodology and the MPACT-CTF solutions are provided for a single pin case. Good power and eigenvalue agreement (+/−4%, 352[pcm] respectively) is achieved at hot full power conditions.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5004-6
PROCEEDINGS PAPER
Development of an MCNP6-ANSYS FLUENT Multiphysics Coupling Capability
William Gurecky,
William Gurecky
The University of Texas at Austin, Austin, TX
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Erich Schneider
Erich Schneider
The University of Texas at Austin, Austin, TX
Search for other works by this author on:
William Gurecky
The University of Texas at Austin, Austin, TX
Erich Schneider
The University of Texas at Austin, Austin, TX
Paper No:
ICONE24-60937, V004T10A028; 6 pages
Published Online:
October 25, 2016
Citation
Gurecky, W, & Schneider, E. "Development of an MCNP6-ANSYS FLUENT Multiphysics Coupling Capability." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management. Charlotte, North Carolina, USA. June 26–30, 2016. V004T10A028. ASME. https://doi.org/10.1115/ICONE24-60937
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