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Technical Papers

Direct Comparison of High-Order/Low-Order Transient Methods on the 2D-LRA Benchmark Problem

ORCID Icon, &
Pages 409-432 | Received 19 Jul 2021, Accepted 07 Sep 2021, Published online: 21 Dec 2021

References

  • B. SJENITZER and J. HOOGENBOOM, “General Purpose Dynamic Monte Carlo with Continuous Energy for Transient Analysis,” Proc. PHYSOR 2012, Knoxville, Tennessee, April 15–20, 2012, American Nuclear Society (2012).
  • V. VALTAVIRTA, M. HESSAN, and J. LEPPÄNEN, “Delayed Neutron Emission Model for Time Dependent Simulations with the SERPENT 2 Monte Carlo Code—First Results,” Proc. PHYSOR 2016, Sun Valley, Idaho, May 1–5, 2016, American Nuclear Society (2016).
  • D. FERRARO et al., “SERPENT and TRIPOLI-4 Transient Calculations Comparisons for Several Reactivity Insertion Scenarios in a 3D Minicore Benchmark,” Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2019), Portland, Oregon, August 25–29, 2019, American Nuclear Society (2019).
  • L. LI, “A Low Order Acceleration Scheme for Solving the Neutron Transport Equation,” PhD Thesis, Massachusetts Institute of Technology, Nuclear Science & Engineering (2013).
  • L. JAIN, R. KARTHIKEYAN, and U. KANNAN, “Multi-Grid Acceleration Scheme for Neutron Transport Calculations Using Optimally Diffusion CMFD Method,” Proc. Symp. Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety, Bombay, India, December 15–19, 2018.
  • B. CHANG et al., “Spatial Multigrid for Isotropic Neutron Transport,” SIAM J. Sci. Comput., 29, 5, 1900 (2007); https://doi.org/https://doi.org/10.1137/060661363.
  • J. YOON and H. JOO, “Two-Level Coarse Mesh Finite Difference Formulation with Multigroup Source Expansion Nodal Kernels,” J. Nucl. Sci. Technol., 45, 7, 668 (2008); https://doi.org/https://doi.org/10.1080/18811248.2008.9711467.
  • C. BENTLEY, “Improvements in a Hybrid Stochastic/Deterministic Method for Transient Three-Dimensional Neutron Transport,” PhD Thesis, University of Tennessee Knoxville, Nuclear Engineering (1996).
  • S. SHANER, “Development of High Fidelity Methods for 3D Monte Carlo Analysis of Nuclear Reactors,” PhD Thesis, Massachusetts Institute of Technology, Nuclear Science & Engineering (2018).
  • BENCHMARK PROBLEM COMMITTEE, “Argonne Code Center: Benchmark Problem Book,” ANL-7416 and Suppl. 2, Argonne National Laboratory (1977).
  • M. ABDO, R. ELZOHERY, and J. ROBERT, “Analysis of the LRA Reactor Benchmark Using Dynamic Mode Decomposition,” Trans. Am. Nucl. Soc., 119, 683 (2018).
  • K. SMITH, “An Analytical Nodal Method for Solving the Two Group, Multidimensional, Static and Transient Neutron Diffusion Equation,” Master Thesis, Massachusetts Institute of Technology, Nuclear Science & Engineering (1979).
  • J. BANFIELD, “Semi-Implicit Direct Kinetics Methodology for Deterministic, Time-Dependent, Three-Dimensional, and Fine-Energy Neutron Transport Solutions,” PhD Thesis, University of Tennessee Knoxville, Nuclear Engineering (2013).
  • B. BANDINI, “A Three-Dimensional Transient Neutronics Routine for the TRAC-PF1 Reactor Thermal Hydraulic Computer Code,” PhD Thesis, The Pennsylvania State University, Nuclear Engineering (1990).
  • Q. WU et al., “Whole-Core Forward-Adjoint Neutron Transport Solutions with Coupled 2-D MOC and 1-D SN and Kinetics Parameter Calculation,” Prog. Nucl. Energy, 108, 310 (2018); https://doi.org/https://doi.org/10.1016/j.pnucene.2018.06.006.
  • J. YASINSKY and A. HENRY, “Some Numerical Experiments Concerning Space-Time Reactor Kinetics Behavior,” Nucl. Sci. Eng., 22, 2, 171 (1965); https://doi.org/https://doi.org/10.13182/NSE65-A20236.
  • Z. PRINCE and J. RAGUSA, “Multiphysics Reactor-Core Simulations Using the Improved Quasi-Static Method,” Ann. Nucl. Energy, 125, 186 (2019); https://doi.org/https://doi.org/10.1016/j.anucene.2018.10.056.
  • A. AL-MOHY and N. HIGHAM, “A New Scaling and Squaring Algorithm for the Matrix Exponential,” SIAM J. Matrix Anal. Appl., 31, 3, 970 (2009); https://doi.org/https://doi.org/10.1137/09074721X.
  • D. FERGUSON and K. HANSEN, “Solution of the Space-Dependent Reactor Kinetics Equations in Three Dimensions,” MIT-2903-4, U.S. Atomic Energy Commission (1971).
  • M. ORTEGA, “A Rayleigh Quotient Fixed Point Method for Criticality Eigenvalue Problems in Neutron Transport,” PhD Thesis, University of California Berkeley, Nuclear Engineering (2019).
  • T. HILL, “Efficient Methods for Time Absorption (α) Eigenvalue Calculations,” LA-9602-MS, Los Alamos National Laboratory (1983).
  • C. JOSEY and F. BROWN, “A New Monte Carlo Alpha-Eigenvalue Estimator with Delayed Neutrons,” Trans. Am. Nucl. Soc., 118, 903 (2018).
  • K. OTT and D. MENELEY, “Accuracy of the Quasistatic Treatment of Spatial Reactor Kinetics,” Nucl. Sci. Eng., 26, 563 (1969); https://doi.org/https://doi.org/10.13182/NSE36-402.
  • Z. PRINCE, “Improved Quasi-Static Methods for Time-Dependent Neutron Diffusion and Implementation in Rattlesnake,” Master Thesis, Texas A&M University (2017).
  • K. OTT, “Quasistatic Treatment of Spatial Phenomena in Reactor Dynamics,” Nucl. Sci. Eng., 26, 563 (1966); https://doi.org/https://doi.org/10.13182/NSE66-A18428.
  • “SIMULATE-3K Models & Methodology Rev. 7,” Studsvik Scandpower (2011).
  • T. SUTTON and B. AVILES, “Diffusion Theory Methods for Spatial Kinetics Calculations,” Prog. Nucl. Energy, 30, 2, 119 (1996); https://doi.org/https://doi.org/10.1016/0149-1970(95)00082-U.