Optimizing Monte Carlo to Multiple Responses: The Direct Statistical Approach, 10 Years On

References

• X-5 MONTE CARLO TEAM, “MCNP—AGeneral Monte Carlo N-Particle Transport Code, Version 5, Vols. I–III,” LAUR-03-1987, LA-CP-03-0245, LA-CP-03-0284, Los Alamos National Laboratory (2003) (revised 2005).
   Google Scholar
• A. DUBI, “General Statistical Model for Geometrical Splitting in Monte Carlo—Parts I and II,” Trans. Theory Stat. Phys., 14-2, 167 and 195 (1985).
   Google Scholar
• K. W. BURN, “Extension of the Direct Statistical Approach to a Volume Parameter Model (Non-Integer Splitting),” Ann. Nucl. Energy, 17-6, 293 (1990).
   Web of Science ®Google Scholar
• K. W. BURN, “Optimizing Cell Importances Using an Extension of the DSA—Theory, Implementation, Preliminary Results,” Prog. Nucl. Energy, 24, 39 (1990).
   Web of Science ®Google Scholar
• K. W. BURN, “Complete Optimization of Space/Energy Cell Importances with the DSA Cell Importance Model,” Ann. Nucl. Energy, 19-2, 65 (1992).
   Web of Science ®Google Scholar
• K. W. BURN, “Extending the Direct Statistical Approach to Include Particle Bifurcation Between the Splitting Surfaces,” Nucl. Sci. Eng., 119, 44 (1995).
   Web of Science ®Google Scholar
• K. W. BURN, “A New Weight-Dependent Direct Statistical Approach Model,” Nucl. Sci. Eng., 125, 128 (1997).
   Web of Science ®Google Scholar
• T. E. BOOTH and K. W. BURN, “Some Sample Problem Comparisons Between the DSA Cell Model and the Quasi-Deterministic Method,” Ann. Nucl. Energy, 20-11, 733 (1993).
   Web of Science ®Google Scholar
• K. W. BURN, “Learning Aspects of the Direct Statistical Approach to the Optimization of Monte Carlo Radiation Transport Calculations,” presented at Workshop on Adaptive Monte Carlo Methods, Los Alamos, New Mexico, August 1996.
   Google Scholar
• K. W. BURN and E. NAVA, “Optimization of Variance Reduction Parameters in Monte Carlo Radiation Transport Calculations to a Number of Responses of Interest,” Proc. Int. Conf. Nuclear Data for Science and Technology, Trieste, Italy, p. 260, Italian Physical Society (1997).
   Google Scholar
• K. W. BURN, G. F. GUALDRINI, and E. NAVA, “Variance Reduction with Multiple Responses,” Proc. Monte Carlo 2000, Lisbon, Portugal, October 23–26, 2000, Springer (2001).
   Google Scholar
• M. A. COOPER and E. W. LARSEN, “Automated Weight Windows for Global Monte Carlo Particle Transport Calculations,” Nucl. Sci. Eng., 137, 1 (2001).
   Web of Science ®Google Scholar
• T. L. BECKER, A. B. WOLLABER, and E. W. LARSEN, “AHybrid Monte Carlo–Deterministic Method for Global Particle Transport Calculations,” Nucl. Sci. Eng., 155, 155 (2007).
   Web of Science ®Google Scholar
• J. C. WAGNER, E. D. BLAKEMAN, and D. E. PEPLOW, “Forward-Weighted CADIS Method for Global Variance Reduction,” Trans. Am. Nucl. Soc., 97 630 (2007).
   Google Scholar
• D. E. PEPLOW, “MAVRIC (SCALE),” presented at 2010 Joint Topl. Mtg. Nevada Section of the American Nuclear Society, Las Vegas, Nevada, 2010.
   Google Scholar
• C. J. SOLOMON, A. SOOD, and T. E. BOOTH, “A Weighted Adjoint Source for Weight-Window Generation by Means of a Linear Tally Combination,” Proc. Int. Conf. Mathematics, Computational Methods,&Reactor Physics, Saratoga Springs, New York, May 3–7, 2009, American Nuclear Society (2009) (CD-ROM).
   Google Scholar
• C. J. SOLOMON and A. SOOD, “Duct Streaming Validation Benchmark Calculations with a Global Importance Map,” Trans. Am. Nucl. Soc., 101, 638 (2009).
   Google Scholar
• K. W. BURN and G. F. GUALDRINI, “Optimizing the Monte Carlo Evaluation of Neutron Spectra Within a Thermal Neutron Calibration Facility,” RT/2002/54/ION, ENEA (Feb. 2003).
   Google Scholar
• “MCNP—A General Monte Carlo N-Particle Transport Code, Version 4B,” LA-12625-M, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (1997).
   Google Scholar
• K. W. BURN, L. CASALINI, E. NAVA, C. PETROVICH, and L. TECCHIO, “Shielding Calculations for a 100 MeV 30 mA Proton Beam,” Radiat. Prot. Dosim., 116, 1–4, 89 (2005).
   Web of Science ®Google Scholar
• M. D. CARELLI, L. E. CONWAY, L. ORIANI, B. PETROVIC, C. V. LOMBARDI, M. E. RICOTTI, A. C. O. BARROSO, J. M. COLLADO, L. CINOTTI, N. E. TODREAS, D. GRGIC, M. M. MORAES, R. D. BOROUGHS, H. NINOKATA, D. T. INGERSOLL, and F. ORIOLO, “The Design and Safety Features of the IRIS Reactor,” Nucl. Eng. Des., 230, 151 (2004).
   Web of Science ®Google Scholar
• K. W. BURN, M. SAROTTO, F. FRANCESCHINI, B. PETROVICH, J. JOHNSON, E. PADOVANI, and A. CAMMI, “Evaluation of Radiation Field in the IRIS Nuclear Power Plant Using 3-D Transport Theory Analysis,” presented at 11th Int. Conf. Radiation Shielding (ICRS-11)/15th Topl. Mtg. Radiation Protection and Shielding Division (RPSD-2008), Pine Mountain, Georgia, April 13–18, 2008.
   Google Scholar
• “MCNPXTM User’s Manual Version 2.1.5,” TPO-E83-GUG-X-00001, Rev. 0, L. S. WATERS, Ed., Los Alamos National Laboratory (Nov. 1999).
   Google Scholar