DOI QR코드

DOI QR Code

CHALLENGES AND PROSPECTS FOR WHOLE-CORE MONTE CARLO ANALYSIS

  • Martin, William R. (Department of Nuclear Engineering and Radiological Sciences University of Michigan)
  • Received : 2011.03.23
  • Accepted : 2012.02.19
  • Published : 2012.03.25

Abstract

The advantages for using Monte Carlo methods to analyze full-core reactor configurations include essentially exact representation of geometry and physical phenomena that are important for reactor analysis. But this substantial advantage comes at a substantial cost because of the computational burden, both in terms of memory demand and computational time. This paper focuses on the challenges facing full-core Monte Carlo for keff calculations and the prospects for Monte Carlo becoming a routine tool for reactor analysis.

Keywords

References

  1. X-5 Monte Carlo Team, "MCNP - A General N-Particle Transport Code, Version 5 - Volume I: Overview and Theory," LA-UR-03-1987, Los Alamos National Laboratory (April, 2003).
  2. F. B. Brown, "Recent Advances and Future Prospects for Monte Carlo," Proc. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC2010), Tokyo, Japan, October 17-21, 2010.
  3. F. B. Brown "Monte Carlo Methods in Reactor Physics: Current Status & Future Prospects," presented at the M&C Division Computational Roundtable, American Nuclear Society Summer Meeting, Hollywood, FL, June 27, 2011.
  4. D. Griesheimer "Monte Carlo Methods in Reactor Physics: Current Status and Future Prospects - In-Line Feedback Effects," presented at the M&C Division Computational Roundtable, American Nuclear Society Summer Meeting, Hollywood, FL, June 27, 2011.
  5. K. Smith "Monte Carlo for Practical LWR Analysis: what's needed to get to the goal?, " presented at the M&C Division Computational Roundtable, American Nuclear Society Summer Meeting, Hollywood, FL, June 27, 2011.
  6. J. Wagner "Hybrid and Parallel Domain-Decomposition Methods Development to Enable Monte Carlo for Reactor Analyses," presented at the M&C Division Computational Roundtable, American Nuclear Society Summer Meeting, Hollywood, FL, June 27, 2011.
  7. Hj. Matzke, "On the rim effect in high burnup $UO_{2}$ LWR fuels," J. Nucl. Materials, 189, 141-148 (1992). https://doi.org/10.1016/0022-3115(92)90428-N
  8. M. Rosa, J. S. Warsa, J. H. Chang, and R. S. Baker, "Discrete Ordinate Calculation of the k-Eigenvalue of an IFBA Pin Using Unstructured Meshes in 2D," to be presented at the Summer Meeting of the American Nuclear Society, Chicago, June 2012.
  9. T. M. Sutton, T. J. Donovan, T. H. Trumbull, P. S. Dobreff, E. Caro, D. P. Griesheimer, L. J. Tyburski, D. C. Carpenter, and H. Joo, "The MC21 Monte Carlo Transport Code," Proc. ANS Mathematics & Computation Division Topical Meeting, M&C2007, Monterey, CA, USA, April 2007.
  10. D. J. Kelly, T. M. Sutton, T. H. Trumbull, and P. S. Dobreff, "MC21 Monte Carlo Analysis of the Hoogenboom-Martin Full-Core PWR Benchmark Problem," Proc. ANS Reactor Physics Division Topical Meeting, PHYSOR10, Pittsburgh, May 2010.
  11. T. Sutton, "Progress in Monte Carlo for Reactor Design and Analysis," presentation at the University of Michigan, October 6, 2011.
  12. J. C. Wagner, D. E. Peplow, S. W. Mosher, and T. M. Evans, "Review of Hybrid (Deterministic/Monte Carlo) Radiation Transport Methods, Codes, and Applications at Oak Ridge National Laboratory," Proc. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC2010), Tokyo, Japan, October 17-21, 2010.
  13. A. Siegel, K. Smith, P. Fischer, and V. Mahadevan, "Analysis of Communication Costs for Domain Decomposed Monte Carlo Methods in Nuclear Reactor Analysis," accepted for publication, J. Comp. Phys. (December 2011), http://dx. doi.org/10. 1016/j. jcp. 2011. 12. 014.
  14. T. Kitada and T. Takeda, "Effective Convergence of Fission Source Distribution in Monte Carlo Simulation," J. Nucl. Sci. Technol., 38, 324-329 (2001). https://doi.org/10.3327/jnst.38.324
  15. T. Ueki and F. B. Brown, "Stationarity Modeling and Informatics-Based Diagnostics in Monte Carlo Criticality Calculations," Nucl. Sci. Eng., 149, 38-50 (2005). https://doi.org/10.13182/NSE04-15
  16. M. -J. Lee, H. G. Joo, D. Lee, and K. Smith, "Multigroup Monte Carlo Reactor Calculation with Coarse Mesh Finite Difference Formulation for Real Variance Reduction," Proc. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC2010), Tokyo, Japan, October 17-21, 2010.
  17. E. W. Larsen and J. Yang "A Functional Monte Carlo Method for k-Eigenvalue Problems," Nucl. Sci. Eng., 159, 107-126 (2008). https://doi.org/10.13182/NSE07-92
  18. J. Yang and E. W. Larsen, "Application of the 'Functional Monte Carlo' Method to Estimate Continuous Energy k- Eigenvalues and Eigenfunctions," Proc. ANS Mathematics & Computation Division Topical Meeting, M&C2009, Saratoga Springs, New York, USA, 2009.
  19. J. Yang and E. W. Larsen, "Calculation of k-Eigenvalues and Multi-Group Eigenfunctions Using the Hybrid 'Functional Monte Carlo' Method," Proc. ANS Reactor Physics Division Topical Meeting, PHYSOR10, Pittsburgh, May 2010.
  20. E. R. Wolters, E. W. Larsen, and W. R. Martin, "Generalized Hybrid Monte Carlo - CMFD Methods for Fission Source Convergence," Proc. ANS Mathematics & Computation Division Topical Meeting, M&C2011, Rio de Janeiro, Brazil, May 8-12, 2011.
  21. T. Ueki, T. Mori, and M. Nakagawa, "Error Estimation and their Biases in Monte Carlo Eigenvalue Calculations," Nucl. Sci. Eng., 125, 1-11 (1997). https://doi.org/10.13182/NSE97-1
  22. E. M. Gelbard and R. Prael, "Computation of Standard Deviations in Eigenvalue Calculations," Prog. Nucl. Energy, 24, 237 (1990). https://doi.org/10.1016/0149-1970(90)90041-3
  23. T. Ueki, "Intergenerational Correlation in Monte Carlo k-Eigenvalue Calculation," Nucl. Sci. Eng., 141, 101-110 (2002). https://doi.org/10.13182/NSE141-101
  24. H. J. Shim, Y. Kim, and C. H. Kim, History-Based Batch Method for a Real Variance Estimation in Monte Carlo Eigenvalue Calculations, Trans. Am. Nucl. Soc., 100, 300 (2009).
  25. F. B. Brown, "A Review of Monte Carlo Criticality Calculations - Convergence, Bias, Statistics," Proc. ANS Mathematics & Computation Division Topical Meeting, M&C2009, Saratoga Springs, NY, May 3-7, 2009.
  26. F. B. Brown, "K-Effective of the World and other Concerns for Monte Carlo Eigenvalue Problems," Proc. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC2010), Tokyo, Japan, May 3-7, 2009.
  27. B. C. Kiedrowski and F. B. Brown, "Using Wielandt's method to eliminate confidence interval under prediction bias in MCNP5 criticality calculations," Trans. Am. Nucl. Soc., 99, 338-340 (2008).
  28. H. J. Shim and C. H. Kim, "Tally Efficiency Analysis for Monte Carlo Wielandt Method," Ann. Nucl. Eng., 36, 1694-1701 (2009). https://doi.org/10.1016/j.anucene.2009.09.004
  29. B. R. Betzler, E. E. Sunny, J. C. Lee, and W. R. Martin, "Coupled Nuclear-Thermal- Hydraulic Calculations for Fort St. Vrain Reactor," Proc. 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-14), Toronto, Canada, September 25-29, 2011.
  30. RELAP5-3D Code Development Team, "ATHENA Code Manual," INEEL-EXT-98-00834, Rev. 2. 2, Idaho National Engineering and Environmental Laboratory (2003).
  31. D. A. Knoll and D. E. Keyes, "Jacobian-free Newton-Krylov methods: a survey of approaches and applications," J. Comp. Phys., 193, pp. 357-397 (2004). https://doi.org/10.1016/j.jcp.2003.08.010
  32. H. Park, D. A. Knoll, D. R. Gaston, and R. C. Martineau, "Tightly Coupled Multiphysics Algorithms for Pebble Bed Reactors," Nucl. Sci. Eng., 166, 118-133 (2010). https://doi.org/10.13182/NSE09-104
  33. D. P. Griesheimer, W. R. Martin, and J. P. Holloway, "Convergence Properties of Monte Carlo Functional Expansion Tallies," J. Comp. Phys., 211, 129-153 (January 2006). https://doi.org/10.1016/j.jcp.2005.05.023
  34. K. Banerjee and W. R. Martin, "Kernel Density Estimated Monte Carlo Global Flux Tallies," Proc. ANS Mathematics & Computation Division Topical Meeting, M&C2009, Saratoga Springs, NY, May 3-7, 2009.
  35. K. Banerjee and W. R. Martin, "Kernel Density Estimation Method for Monte Carlo Global Flux Tallies," accepted for publication, Nucl. Sci. Eng. (2011).
  36. R. E. MacFarlane and D. W. Muir, "NJOY99.0 Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data," PSR-480/NJOY99.00, Los Alamos National Laboratory, Los Alamos (1999).
  37. T. H. Trumbull, "Treatment of Nuclear Data for Transport Problems Containing Detailed Temperature Distributions, " Nucl. Technol., 156, 75-86 (2006). https://doi.org/10.13182/NT156-75
  38. J. L. Conlin, W. Ji, J. C. Lee, and W. R. Martin, "Pseudo Material Construct for Coupled Neutronic-Thermal-Hydraulic Analysis of VHTGR," Trans. Am. Nucl. Soc., 92, 225-227, San Diego, CA (June, 2005).
  39. G. Yesilyurt, W. R. Martin, and F. B. Brown, "On-the-Fly Doppler Broadening for Monte Carlo Codes," accepted for publication, Nucl. Sci. Eng. (2011).
  40. F. B. Brown, W. R. Martin, G. Yesilyurt, and S. Wilderman, "Progress with On-The-Fly Neutron Doppler Broadening in MCNP," to be presented at the Summer Meeting of the American Nuclear Society, Chicago, June 2012. Also LAUR-12-00423, Los Alamos National Laboratory (2012).
  41. Y. Nagaya, K. Okumura, T. Mori, and M. Nakagawa, "MVP/GMVP II: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods, " JAERI 1348 (2004).
  42. 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 Revision 1. 1, http://www. nea. fr/dbprog/MonteCarloPerformanceBenchmark. htm (2010).
  43. J. E. Hoogenboom and W. R. Martin, "A Proposal for a Benchmark to Monitor the Performance of Detailed Monte Carlo Calculation of Power Densities in a Full Size Reactor Core, " Proc. ANS Mathematics & Computation Division Topical Meeting, M&C2009, Saratoga Springs, NY, May 3-7, 2009.
  44. K. Smith, "Reactor Core Methods," Invited lecture, ANS Mathematics & Computation Division Topical Meeting, M&C2003, Gatlinburg, TN, USA, April 2003. URL: http://www.nea.fr/html/dbprog/documents/ MC03Smith.pdf.
  45. W. R. Martin "Advances in Monte Carlo Methods for Global Reactor Analysis," Invited lecture, ANS Mathematics & Computation Division Topical Meeting, M&C2007, Monterey, CA, USA, April 2007. URL: http://www.nea.fr/html/dbprog/documents/M&C07Martin.pdf.
  46. J. E. Hoogenboom, W. R. Martin, and B. Petrovic, "The Monte Carlo Performance Benchmark Test - Aims, Specifications, and First Results," Proc. ANS Mathematics & Computation Division Topical Meeting, M&C2011, Rio de Janeiro, Brazil, May 8-12, 2011.
  47. J. Leppänen "Use of the Serpent Monte Carlo Reactor Physics Code for Full-Core Calculations" Proc. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC2010), Tokyo, Japan, October 17-21, 2010.

Cited by

  1. Impact of Dynamic Condensation of Energy Groups on Convergence Behavior of One-Node CMFD Method for Neutron Diffusion Problem vol.174, pp.3, 2013, https://doi.org/10.13182/NSE12-27
  2. Data decomposition in Monte Carlo neutron transport simulations using global view arrays vol.29, pp.3, 2015, https://doi.org/10.1177/1094342015577681
  3. Preliminary Coupling of the Monte Carlo Code OpenMC and the Multiphysics Object-Oriented Simulation Environment for Analyzing Doppler Feedback in Monte Carlo Simulations vol.185, pp.1, 2017, https://doi.org/10.13182/NSE16-26
  4. Exploring versioned distributed arrays for resilience in scientific applications vol.31, pp.6, 2017, https://doi.org/10.1177/1094342016664796
  5. Multi-Regional Delta-Tracking Method for Neutron Transport Tracking in Monte Carlo Criticality Calculation vol.10, pp.7, 2018, https://doi.org/10.3390/su10072272