578
Views
2
CrossRef citations to date
0
Altmetric
Research Articles

Multiphysics Analysis System for Heat Pipe–Cooled Micro Reactors Employing PRAGMA-OpenFOAM-ANLHTP

ORCID Icon, , ORCID Icon, ORCID Icon, & ORCID Icon
Pages 1743-1757 | Received 19 Aug 2022, Accepted 31 Oct 2022, Published online: 11 Jan 2023

References

  • M. A. GIBSON et al., “Kilopower Reactor Using Stirling TechnologY (KRUSTY) Nuclear Ground Test Results and Lessons Learned,” NASA/TM-2018-219941, U.S. National Aeronautics and Space Administration (2018); https://doi.org/10.2514/6.2018-4973.
  • P. R. MCCLURE et al., “Design of Megawatt Power Level Heat Pipe Reactors,” LA-UR-15-28840, Los Alamos National Laboratory (2015); https://doi.org/10.2172/1226133.
  • M. M. SWARTZ et al., “Westinghouse eVinci™ Heat Pipe Micro Reactor Technology Development,” Proc. 2021 28th Int. Conf. on Nuclear Engineering, August 4–6, 2021, Vol. 85246, p. V001T04A018 (2021).
  • “OKLO Part II: Final Safety Analysis Report,” U.S. Nuclear Regulatory Commission (2020); https://www.nrc.gov/docs/ML2007/ML20075A003.pdf.
  • H. JASAK, “OpenFOAM: Open Source CFD in Research and Industry,” Int. J. Nav. Archit. Ocean Eng., 1, 2, 89 (2009).
  • C. FIORINA et al., “GeN-Foam: A Novel OpenFOAM® Based Multi-Physics Solver for 2D/3D Transient Analysis of Nuclear Reactors,” Nucl. Eng. Des., 294, 24 (2015); https://doi.org/10.1016/j.nucengdes.2015.05.035.
  • M. AUFIERO et al., “Serpent-OpenFOAM Coupling in Transient Mode: Simulation of a Godiva Prompt Critical Burst” Proc. Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science & Engineering, Nashville, Tennessee, April 19–23, 2015.
  • M. J. JEONG, S. LEE, and H. K. CHO, “Verification and Validation of the OpenFOAM Stress Analysis Solver for Heat Pipe Cooled Micro Reactor Simulation,” Proc. 19th Int. Top;. Mtg. on Nuclear Reactor Thermal Hydraulics (NURETH-19), March 6, 2022.
  • N. CHOI, K. M. KIN, and H. G. JOO, “Optimization of Neutron Tracking Algorithms for GPU-based Continuous Energy Monte Carlo Calculation,” Ann. Nucl. Energy, 162, 108508 (2021); https://doi.org/10.1016/j.anucene.2021.108508.
  • J. LEPPÄNEN and M. AUFIERO, “Development of an Unstructured Mesh Based Geometry Model in the Serpent 2 Monte Carlo Code,” Proc. PHYSOR 2014, Kyoto, Japan (2014).
  • S. G. PARKER et al., “OptiX: A General Purpose Ray Tracing Engine,” ACM Trans. Graphics, 29, 4, 1 (2010); https://doi.org/10.1145/1778765.1778803.
  • R. BERGMANN and J. VUJIĆ, “Algorithmic Choices in WARP—A Framework for Continuous Energy Monte Carlo Neutron Transport in General 3D Geometries on GPUs,” Ann. Nucl. Energy, 77, 176 (2015); https://doi.org/10.1016/j.anucene.2014.10.039.
  • J. SALMON and S. SMITH, “Exploiting Hardware-Accelerated Ray Tracing for Monte Carlo Particle Transport with OpenMC,” Proc. 10th Int. Workshop on Performance Modeling, Benchmarking, and Simulation of High Performance Computer Systems (PMBS), p. 19 (2019).
  • G. A. MCLENNAN, “ANL/HTP: A Computer Code for the Simulation of Heat Pipe Operation,” ANL-83-108, Argonne National Laboratory (1983); https://digital.library.unt.edu/ark:/67531/metadc283626.
  • J. IM, N. CHOI, and H. G. JOO, “Flexible Geometry Treatment in PRAGMA Using NVIDIA® Ray Tracing Engine OptiX™,” Trans. Korean Nuclear Society Virtual Spring Mtg., July 9, 2020.
  • “Coreform Cubit Version 2022.6 [Computer Software],” Coreform LLC, ( 2022); http://coreform.com.
  • A. WOO, A. PEARCE, and M. OUELLETTE, “It’s Really Not a Rendering Bug, You See,” IEEE Comput. Graphics Appl., 16, 5, 21 (1996); https://doi.org/10.1109/38.536271.
  • S. G. POPOV et al., “Thermophysical Properties of MOX and UO2 Fuels Including the Effects of Irradiation,” ORNL/TM-2000/351, Oak Ridge National Laboratory (2000).
  • C. S. KIM, “Thermophysical Properties of Stainless Steels,” ANL-75-55, Argonne National Laboratory (1975).
  • F. R. CAMPBELL et al., “In-Reactor Measurement of Fuel-to-Sheath Heat Transfer Coefficients Between UO2 and Stainless Steel,” AECL-5400, Atomic Energy of Canada Ltd. (1977).
  • C. H. LEE, Y. S. JUNG, and H. K. CHO, “Micro Reactor Simulation Using the PROTEUS Suite in FY19,” ANL/NSE-19/33, Argonne National Laboratory (2019).
  • J. DUFEK and K. TUTTELBERG, “Monte Carlo Criticality Calculations Accelerated by a Growing Neutron Population,” Ann. Nucl. Energy, 94, 16 (2016); https://doi.org/10.1016/j.anucene.2016.02.015.
  • J. W. STERBENTZ et al., “Special Purpose Nuclear Reactor (5 MW) for Reliable Power at Remote Sites Assessment Report,” INL/EXT-16-40741, Idaho National Laboratory (2017).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.