The RAPID Fission Matrix Approach to Reactor Core Criticality Calculations

References

• T. YAMAMOTO, T. NAKAMURA, and Y. MIYOSHI, “Fission Source Convergence of Monte Carlo Criticality Calculations in Weakly Coupled Fissile Arrays,” J. Nucl. Sci. Technol., 37, 1, 41 (2000); https://doi.org/10.1080/18811248.2000.9714865.
   Web of Science ®Google Scholar
• T. UEKI et al., “Autocorrelation and Dominance Ratio in Monte Carlo Criticality Calculations,” Nucl. Sci. Eng., 145, 3, 279 (2003); https://doi.org/10.13182/NSE03-04.
   Web of Science ®Google Scholar
• L. MAYHUE et al., “Qualification of NEXUS/ANC Nuclear Design System for PWR Analyses,” Proc. Int. Conf. Physics of Reactors—Nuclear Power: A Sustainable Resource (PHYSOR 2008), Interlaken, Switzerland, September 14–19, 2008.
   Google Scholar
• T. BAHADIR and S.-Ö. LINDAHL, “Studsvik’s Next Generation Nodal Code SIMULATE-5,” Proc. Advances in Nuclear Fuel Management (ANFM IV), Hilton Head, South Carolina, April 12–15, 2009, American Nuclear Society (2009).
   Google Scholar
• T. J. DOWNAR et al., “PARCS: Purdue Advanced Reactor Core Simulator,” Proc. Int. Conf. Physics of Reactors—New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002), Seoul, Korea, October 7–10, 2002, American Nuclear Society (2002).
   Google Scholar
• B. COLLINS et al., “Stability and Accuracy of 3D Neutron Transport Simulations Using the 2D/1D Method in MPACT,” J. Comput. Phys., 326, 612 (2016); https://doi.org/10.1016/j.jcp.2016.08.022.
   Web of Science ®Google Scholar
• E. R. SHEMON, M. A. SMITH, and C. H. LEE, “Proteus-SN Methodology Manual,” ANL/NE-14/5, Argonne National Laboratory (2014).
   Google Scholar
• M. RYU et al., “Solution of the BEAVRS Benchmark Using the nTRACER Direct Whole Core Calculation Code,” J. Nucl. Sci. Technol., 52, 7–8, 961 (2015); https://doi.org/10.1080/00223131.2015.1038664.
   Web of Science ®Google Scholar
• T. KITADA and T. TAKEDA, “Effective Convergence of Fission Source Distribution in Monte Carlo Simulation,” J. Nucl. Sci. Technol., 38, 5, 324 (2001); https://doi.org/10.1080/18811248.2001.9715036.
   Web of Science ®Google Scholar
• J. DUFEK and W. GUDOWSKI, “Fission Matrix Based Monte Carlo Criticality Calculations,” Ann. Nucl. Energy, 36, 8, 1270 (2009); https://doi.org/10.1016/j.anucene.2009.05.003.
   Web of Science ®Google Scholar
• W. J. WALTERS et al., “Calculation of Sub-Critical Multiplication Using a Simplified Fission Matrix Method,” Trans. Am. Nucl. Soc., 101, 447 (2009).
   Google Scholar
• M. WENNER and A. HAGHIGHAT, “A Fission Matrix Based Methodology for Achieving an Unbiased Solution for Eigenvalue Monte Carlo Simulations,” Prog. Nucl. Sci. Technol., 2, 886 (2011); https://doi.org/10.15669/pnst.2.886.
   Google Scholar
• D. SHE, J. LIANG, and K. WANG, “Undersampling Diagnostics by Fission Matrix in Monte Carlo Criticality Calculations,” Ann. Nucl. Energy, 62, 321 (2013); https://doi.org/10.1016/j.anucene.2013.05.037.
   Web of Science ®Google Scholar
• S. CARNEY et al., “Theory and Applications of the Fission Matrix Method for Continuous-Energy Monte Carlo,” Ann. Nucl. Energy, 73, 423 (2014); https://doi.org/10.1016/j.anucene.2014.07.020.
   Web of Science ®Google Scholar
• W. J. WALTERS et al., “Use of the Fission Matrix Method for Solution of the Eigenvalue Problem in a Spent Fuel Pool,” Proc. Int. Conf. Physics of Reactors—The Role of Reactor Physics Toward a Sustainable Future (PHYSOR 2014), Kyoto, Japan, September 28–October 3, 2014.
   Google Scholar
• J. W. NIELSEN, D. W. NIGG, and A. W. LaPORTA, “A Fission Matrix Based Validation Protocol for Computed Power Distributions in the Advanced Test Reactor,” Nucl. Eng. Des., 295, 615 (2015); https://doi.org/10.1016/j.nucengdes.2015.07.049.
   Web of Science ®Google Scholar
• A. LAUREAU et al., “Transient Fission Matrix: Kinetic Calculation and Kinetic Parameters βeff and Λeff Calculation,” Ann. Nucl. Energy, 85, 1035 (2015); https://doi.org/10.1016/j.anucene.2015.07.023.
   Web of Science ®Google Scholar
• L. PAN, R. WANG, and S. JIANG, “Monte Carlo Fission Matrix Acceleration Method with Limited Inner Iteration,” Nucl. Sci. Eng., 180, 2, 199 (2015); https://doi.org/10.13182/NSE14-73.
   Web of Science ®Google Scholar
• W. J. WALTERS, N. J. ROSKOFF, and A. HAGHIGHAT, “A Fission Matrix Approach to Calculate Pin-Wise 3-D Fission Density Distribution,” Proc. Mathematics & Computation, Nashville, Tennessee, April 19–23, 2015, American Nuclear Society (2015).
   Google Scholar
• A. HAGHIGHAT, Monte Carlo Methods for Particle Transport, CRC Press (2016).
   Google Scholar
• J. DUFEK and G. HOLST, “Correlation of Errors in the Monte Carlo Fission Source and the Fission Matrix Fundamental-Mode Eigenvector,” Ann. Nucl. Energy, 94, 415 (2016); https://doi.org/10.1016/j.anucene.2016.04.013.
   Web of Science ®Google Scholar
• W. J. WALTERS, “Application of the RAPID Fission Matrix Methodology to 3-D Whole-Core Reactor Transport,” Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, April 16–20, 2017.
   Google Scholar
• N. J. ROSKOFF et al., “Benchmarking of the RAPID Tool for a Subcritical Facility,” Proc. 57th INMM Annual Mtg., Atlanta, Georgia, July 24–28, 2016, Institute of Nuclear Materials Management (2016).
   Google Scholar
• A. HAGHIGHAT, W. J. WALTERS, and N. J. ROSKOFF, “RAPID Particle Transport Methodology for Real-Time Simulation of Nuclear Systems,” Provisional U.S. patent application 62/582,709 (2017).
   Google Scholar
• A. HAGHIGHAT, K. E. ROYSTON, and W. J. WALTERS, “MRT Methodologies for Real-Time Simulation of Nonproliferation and Safeguards Problems,” Ann. Nucl. Energy, 87, 61 (2016); https://doi.org/10.1016/j.anucene.2015.06.004.
   Web of Science ®Google Scholar
• J. E. HOOGENBOOM, W. R. MARTIN, and B. PETROVIC, “Monte Carlo Performance Benchmark for Detailed Power Density Calculation in a Full Size Reactor Core,” Benchmark Specifications Rev. 1.2, Organisation for Economic Co-operation and Development Nuclear Energy Agency (July 2011).
   Google Scholar
• N. J. ROSKOFF and A. HAGHIGHAT, “Development of a Novel Fuel Burnup Methodology Using the RAPID Particle Transport Code System,” Proc. Int. Conf. Physics of Reactors—Reactor Physics Paving the Way Towards More Efficient Systems (PHYSOR 2018), Cancun, Mexico, April 22–26, 2018.
   Google Scholar
• A. RAU and W. J. WALTERS, “Application of Fission Matrix Correction Method to TRIGA Reactor Core,” Trans. Am. Nucl. Soc., 118, 1014 (2018).
   Google Scholar
• K. MORTON, “Criticality Calculations by Monte Carlo Methods,” T/R-1903, United Kingdom Atomic Energy Research Establishment, Harwell (1956).
   Google Scholar
• E. KAPLAN, “Monte Carlo Methods for Equilibrium Solutions in Neutron Multiplication,” UCRL-5275-T, Lawrence Livermore National Laboratory (1958).
   Google Scholar
• L. CARTER and N. McCORMICK, “Source Convergence in Monte Carlo Calculations,” Nucl. Sci. Eng., 36, 3, 438 (1969); https://doi.org/10.13182/NSE69-1.
   Web of Science ®Google Scholar
• S. M. BOWMAN, “SCALE 6: Comprehensive Nuclear Safety Analysis Code System,” Nucl. Technol., 174, 2, 126 (2011); https://doi.org/10.13182/NT10-163.
   Web of Science ®Google Scholar
• E. BRUN et al., “Tripoli-4, CEA, EDF and AREVA Reference Monte Carlo Code,” Ann. Nucl. Energy, 82, 151 (2015); https://doi.org/10.1016/j.anucene.2014.07.053.
   Web of Science ®Google Scholar
• J. LEPPÄNEN et al., “The Serpent Monte Carlo Code: Status, Development and Applications in 2013,” Ann. Nucl. Energy, 82, 142 (2015); https://doi.org/10.1016/j.anucene.2014.08.024.
   Web of Science ®Google Scholar
• N. J. ROSKOFF, A. HAGHIGHAT, and V. MASCOLINO, “Experimental and Computational Validation of RAPID,” Proc. 16th Int. Symp. Reactor Dosimetry, Santa Fe, New Mexico, May 7–12, 2017.
   Google Scholar
• D. HE and W. J. WALTERS, “A New Fission Matrix Correction Method to Estimate the Source Distribution in Nuclear Reactor Core,” Proc. Int. Conf. Physics of Reactors—Reactor Physics Paving the Way Towards More Efficient Systems (PHYSOR 2018), Cancun, Mexico, April 22–26, 2018.
   Google Scholar
• V. MASCOLINO, A. HAGHIGHAT, and N. J. ROSKOFF, “Evaluation of RAPID for a UNF Cask Benchmark Problem,” Eur. Phys. J. Web. Conf., 153, 05025 (2017); https://doi.org/10.1051/epjconf/201715305025.
   Google Scholar