Development of an MCNP6-ANSYS fluent multiphysics coupling capability

William Gurecky; Erich Schneider

doi:10.1115/ICONE24-60937

Development of an MCNP6-ANSYS fluent multiphysics coupling capability

William Gurecky, Erich Schneider

Power Reactor Modeling

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

11 Scopus citations

Abstract

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.

Original language	English
Title of host publication	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
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Electronic)	9780791850046
DOIs	https://doi.org/10.1115/ICONE24-60937
State	Published - 2016
Event	2016 24th International Conference on Nuclear Engineering, ICONE 2016 - Charlotte, United States Duration: Jun 26 2016 → Jun 30 2016

Publication series

Name	International Conference on Nuclear Engineering, Proceedings, ICONE
Volume	4

Conference

Conference	2016 24th International Conference on Nuclear Engineering, ICONE 2016
Country/Territory	United States
City	Charlotte
Period	06/26/16 → 06/30/16

Funding

Funding for this work was provided by the Consortium for Advanced Simulation of LWR's (CASL), a U.S. Department of Energy innovation hub based at ORNL.

Access to Document

10.1115/ICONE24-60937

Cite this

Gurecky, W., & Schneider, E. (2016). Development of an MCNP6-ANSYS fluent multiphysics coupling capability. In 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 Article V004T10A028 (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 4). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/ICONE24-60937

Gurecky, William ; Schneider, Erich. / Development of an MCNP6-ANSYS fluent multiphysics coupling capability. 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. American Society of Mechanical Engineers (ASME), 2016. (International Conference on Nuclear Engineering, Proceedings, ICONE).

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abstract = "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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Gurecky, W & Schneider, E 2016, Development of an MCNP6-ANSYS fluent multiphysics coupling capability. in 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., V004T10A028, International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 4, American Society of Mechanical Engineers (ASME), 2016 24th International Conference on Nuclear Engineering, ICONE 2016, Charlotte, United States, 06/26/16. https://doi.org/10.1115/ICONE24-60937

Development of an MCNP6-ANSYS fluent multiphysics coupling capability. / Gurecky, William; Schneider, Erich.
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. American Society of Mechanical Engineers (ASME), 2016. V004T10A028 (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 4).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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Gurecky W, Schneider E. Development of an MCNP6-ANSYS fluent multiphysics coupling capability. In 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. American Society of Mechanical Engineers (ASME). 2016. V004T10A028. (International Conference on Nuclear Engineering, Proceedings, ICONE). doi: 10.1115/ICONE24-60937

Development of an MCNP6-ANSYS fluent multiphysics coupling capability

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