References
- H. G. JOO et al., “Methods and Performance of a Three-Dimensional Whole-Core Transport Code DeCART,” Proc. PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, Illinois, April 25–29, 2004, p. 21, American Nuclear Society (2004).
- D. P. WEBER et al., “High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor,” Nucl. Sci. Eng., 155, 3, 395 (2007); https://doi.org/10.13182/NSE07-A2672.
- Y. S. JUNG et al., “Practical Numerical Reactor Employing Direct Whole Core Neutron Transport and Subchannel Thermal/Hydraulic Solvers,” Ann. Nucl. Energy, 62, 357 (2013); https://doi.org/10.1016/j.anucene.2013.06.031.
- B. KOCHUNAS et al., “VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion,” Nucl. Sci. Eng., 185, 1, 217 (2017); https://doi.org/10.13182/NSE16-39.
- D. J. KELLY et al., “MC21/CTF and VERA Multiphysics Solutions to VERA Core Physics Benchmark Progression Problems 6 and 7,” Nucl. Eng. Technol., 49, 6, 1326 (2017); https://doi.org/10.1016/j.net.2017.07.016.
- J. CHEN et al., “A New High-Fidelity Neutronics Code NECP-X,” Ann. Nucl. Energy, 116, 417 (2018); https://doi.org/10.1016/j.anucene.2018.02.049.
- A. TOTH et al., “Analysis of Anderson Acceleration on a Simplified Neutronics/Thermal Hydraulics System,” Proc. Joint Int. Conf. Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method, Nashville, Tennessee, April 19–23, 2015, Vol. 4, p. 2589, American Nuclear Society (2015).
- S. HAMILTON et al., “An Assessment of Coupling Algorithms for Nuclear Reactor Core Physics Simulations,” J. Comput. Phys., 311, 241 (2016); https://doi.org/10.1016/j.jcp.2016.02.012.
- J. P. SENECAL and W. JI, “Approaches for Mitigating Over-Solving in Multiphysics Simulations,” Int. J. Numer. Meth. Eng., 112, 6, 503 (2017); https://doi.org/10.1002/nme.5516.
- E. D. WALKER, B. COLLINS, and J. C. GEHIN, “Low-Order Multiphysics Coupling Techniques for Nuclear Reactor Applications,” Ann. Nucl. Energy, 132, 327 (2019); https://doi.org/10.1016/j.anucene.2019.04.022.
- D. F. GILL, D. P. GRIESHEIMER, and D. L. AUMILLER, “Numerical Methods in Coupled Monte Carlo and Thermal-Hydraulic Calculations,” Nucl. Sci. Eng., 185, 1, 194 (2017); https://doi.org/10.13182/NSE16-3.
- Z. LIU et al., “An Internal Parallel Coupling Method Based on NECP-X and CTF and Analysis of the Impact of Thermal-Hydraulic Model to the High-Fidelity Calculations,” Ann. Nucl. Energy, 146, 107645 (2020); https://doi.org/10.1016/j.anucene.2020.107645.
- J. YU et al., “Preliminary Coupling of the Thermal/Hydraulic Solvers in the Monte Carlo Code MCS for Practical LWR Analysis,” Ann. Nucl. Energy, 118, 317 (2018); https://doi.org/10.1016/j.anucene.2018.03.043.
- Y. S. JUNG and H. G. JOO, “Decoupled Planar MOC Solution for Dynamic Group Constant Generation in Direct Three-Dimensional Core Calculations,” Proc. Int. Conf. Mathematics, Computational Methods and Reactor Physics (M&C 2009), Saratoga Springs, New York, May 3–7, 2009, Vol. 4, p. 2157, American Nuclear Society (2009).
- B. KOCHUNAS et al., “Overview of Development and Design of MPACT: Michigan Parallel Characteristics Transport Code,” Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2013), Sun Valley, Idaho, May 5–9, 2013, Vol. 1, p. 42, American Nuclear Society (2013).
- F. B. BROWN, “MCNP—A General Monte Carlo N-Particle Transport Code,” LA-UR-03-1987, version 5, Los Alamos National Laboratory (2003).
- P. K. ROMANO and B. FORGET, “The OpenMC Monte Carlo Particle Transport Code,” Ann. Nucl. Energy, 51, 274 (2013); https://doi.org/10.1016/j.anucene.2012.06.040.
- K. SMITH, “Nodal Method Storage Reduction by Nonlinear Iteration,” Trans. Am. Nucl. Soc., 44, 265 (1983).
- K. SMITH and J. RHODES, “Full-Core, 2-D, LWR Core Calculations with CASMO-4E,” Proc. Int. Conf. New Frontiers of Nuclear Technology Reactor Physics, Safety and High-Performance Computing (PHYSOR2002), Seoul, Korea, 2002, p. 7, American Nuclear Society (2002).
- R. E. ALCOUFFE, “Diffusion Synthetic Acceleration Methods for the Diamond-Differenced Discrete-Ordinates Equations,” Nucl. Sci. Eng., 64, 2, 344 (1977); https://doi.org/10.13182/NSE77-1.
- D. A. KNOLL, H. PARK, and C. NEWMAN, “Acceleration of k-Eigenvalue/Criticality Calculations Using the Jacobian-Free Newton-Krylov Method,” Nucl. Sci. Eng., 167, 2, 133 (2011); https://doi.org/10.13182/NSE09-89.
- H. PARK, D. A. KNOLL, and C. K. NEWMAN, “Nonlinear Acceleration of Transport Criticality Problems,” Nucl. Sci. Eng., 172, 1, 52 (2012); https://doi.org/10.13182/NSE11-81.
- B. KOCHUNAS, A. FITZGERALD, and E. LARSEN, “Fourier Analysis of Iteration Schemes for k-Eigenvalue Transport Problems with Flux-Dependent Cross Sections,” J. Comput. Phys., 345, 294 (2017); https://doi.org/10.1016/j.jcp.2017.05.028.
- M. JARRETT et al., “Analysis of Stabilization Techniques for CMFD Acceleration of Neutron Transport Problems,” Nucl. Sci. Eng., 184, 2, 208 (2016); https://doi.org/10.13182/NSE16-51.
- D. WANG and S. XIAO, “A Linear Prolongation Approach to Stabilizing CMFD,” Nucl. Sci. Eng., 190, 1, 45 (2018); https://doi.org/10.1080/00295639.2017.1417347.
- B. C. YEE, B. KOCHUNAS, and E. W. LARSEN, “A Multilevel in Space and Energy Solver for 3-D Multigroup Diffusion and Coarse-Mesh Finite Difference Eigenvalue Problems,” Nucl. Sci. Eng., 193, 7, 722 (2019); https://doi.org/10.1080/00295639.2018.1562777.
- A. ZHU et al., “An Optimally Diffusive Coarse Mesh Finite Difference Method to Accelerate Neutron Transport Calculations,” Ann. Nucl. Energy, 95, 116 (2016); https://doi.org/10.1016/j.anucene.2016.05.004.
- D. WANG and Z. ZHU, “A Revisit to CMFD Schemes: Fourier Analysis and Enhancement,” Energies, 14, 2, 424 (2021); https://doi.org/10.3390/en14020424.
- N. Z. CHO, G. S. LEE, and C. J. PARK, “Partial Current-Based CMFD Acceleration of the 2D/1D Fusion Method for 3D Whole-Core Transport Calculations,” Trans. Am. Nucl. Soc., 88, 594 (2003).
- M. JARRETT et al., “Stabilization Methods for CMFD Acceleration,” Proc. Joint Int. Conf. Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method, Nashville, Tennessee, April 19–23, 2015, Vol. 1, p. 442, American Nuclear Society (2015).
- L. LI, K. SMITH, and B. FORGET, “Techniques for Stabilizing Coarse-Mesh Finite Difference (CMFD) in Methods of Characteristics (MOC),” Proc. Joint Int. Conf. Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method, Nashville, Tennessee, April 19–23, 2015, Vol. 1, p. 480, American Nuclear Society (2015).
- Q. SHEN et al., “Transient Analysis of C5G7-TD Benchmark with MPACT,” Ann. Nucl. Energy, 125, 107 (2019); https://doi.org/10.1016/j.anucene.2018.10.049.
- A. ZHU et al., “Theoretical Convergence Rate Lower Bounds for Variants of Coarse Mesh Finite Difference to Accelerate Neutron Transport Calculations,” Nucl. Sci. Eng., 186, 3, 224 (2017); https://doi.org/10.1080/00295639.2017.1293408.
- Q. SHEN, N. ADAMOWICZ, and B. KOCHUNAS, “Relationship Between Relaxation and Partial Convergence of Nonlinear Diffusion Acceleration for Problems with Feedback,” Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2019), Portland, Oregon, August 25–29, 2019, p. 2248, American Nuclear Society (2019).
- Q. SHEN et al., “X-CMFD: A Robust Iteration Scheme for CMFD-Based Acceleration of Neutron Transport Problems with Nonlinear Feedback,” Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2019), Portland, Oregon, August 25–29, 2019, p. 2238, American Nuclear Society (2019).
- D. WANG, “Application of lpCMFD for k-Eigenvalue Transport Problems with Feedback,” Trans. Am. Nucl. Soc., 123, 681 (2020); https://doi.org/10.13182/T123-32990.
- J. P. SENECAL and W. JI, “Development of an Efficient Tightly Coupled Method for Multiphysics Reactor Transient Analysis,” Prog. Nucl. Energy, 103, 33 (2018); https://doi.org/10.1016/j.pnucene.2017.10.012.
- B. M. KOCHUNAS, “Advanced Simulations of Heterogeneous Light Water Reactor Cores for Transuranic Recycle,” PhD Thesis, University of California, Berkeley (2008).
- B. KOCHUNAS, “Demonstration of Neutronics Coupled to Thermal-Hydraulics for a Full-Core Problem Using COBRA-TF/MPACT,” CASL-U-2014-0051-000, Consortium for the Advanced Simulation of Light Water Reactors (2014).
- S. CHOI et al., “Recent Development Status of Neutron Transport Code STREAM,” Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, 2019.
- B. COLLINS and S. STIMPSON, “Acceleration Methods for Whole Core Reactor Simulations Using VERA,” Trans. Am. Nucl. Soc., 118, 929 (2018).
- M. DAEUBLER et al., “High-Fidelity Coupled Monte Carlo Neutron Transport and Thermal-Hydraulic Simulations Using Serpent 2/SUBCHANFLOW,” Ann. Nucl. Energy, 83, 352 (2015); https://doi.org/10.1016/j.anucene.2015.03.040.
- Q. SHEN, S. CHOI, and B. M. KOCHUNAS, “A Robust, Relaxation-Free Multiphysics Iteration Scheme for CMFD-Accelerated Neutron Transport k-Eigenvalue Calculations—II: Numerical Results,” Nucl. Sci. Eng., 195, 1202 (2021); https://doi.org/10.1080/00295639.2021.1906586.
- Q. SHEN, B. KOCHUNAS, and T. DOWNAR, “Efficient Multiphysics Iterations in MPACT with Partially Convergent CMFD,” EPJ Web of Conferences, 247, 06039 (2021); https://doi.org/10.1051/epjconf/202124706039 (2021).
- A. GRAHAM et al., “Assessment of Thermal-Hydraulic Feedback Models,” Proc. PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho, May 1–5, 2016, Vol. 6, p. 3616, American Nuclear Society (2016).
- M. L. ADAMS and E. W. LARSEN, “Fast Iterative Methods for Discrete-Ordinates Particle Transport Calculations,” Prog. Nucl. Energy, 40, 1, 3 (2002); https://doi.org/10.1016/S0149-1970(01)00023-3.
- N. Z. CHO, “Krylov Subspace Wraps Around the Two-Level p-CMFD Acceleration in the Whole-Core Transport Calculation,” Trans. Am. Nucl. Soc., 123, 1327 (2020); https://doi.org/10.13182/T123-33095.
- B. C. YEE et al., “Space-Dependent Wielandt Shifts for Multigroup Diffusion Eigenvalue Problems,” Nucl. Sci. Eng., 188, 2, 140 (2017); https://doi.org/10.1080/00295639.2017.1350001.
- B. KOCHUNAS, “Theoretical Convergence Rate Analysis of a Unified CMFD Formulation with Various Diffusion Coefficients,” Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2019), Portland, Oregon, August 25–29, 2019, p. 978, American Nuclear Society (2019).
- T. J. DOWNAR et al., “PARCS Purdue Advanced Reactor Core Simulator,” Proc. Int. Conf. New Frontiers of Nuclear Technology Reactor Physics, Safety and High-Performance Computing (PHYSOR2002), Seoul, Korea, 2002, American Nuclear Society (2002).
- Q. SHEN, Y. XU, and T. DOWNAR, “Stability Analysis of the CMFD Scheme with Linear Prolongation,” Ann. Nucl. Energy, 129, 298 (2019); https://doi.org/10.1016/j.anucene.2019.02.011.
- A. FACCHINI, J. LEE, and H. G. JOO, “Investigation of Anderson Acceleration in Neutronics-Thermal Hydraulics Coupled Direct Whole Core Calculation,” Ann. Nucl. Energy, 153, 108042 (Apr. 2021); https://doi.org/10.1016/j.anucene.2020.108042.
- A. TOTH and C. T. KELLEY, “Convergence Analysis for Anderson Acceleration,” SIAM J. Numer. Anal., 53, 2, 805 (2015); https://doi.org/10.1137/130919398.