The Enhancements and Testing for the MCNPX 2.6.0 Depletion Capability

References

• J. S. HENDRICKS, G. W. McKINNEY, H. R. TRELLUE, J. W. DURKEE, T. L. ROBERTS, H. W. EGDORF, J. P. FINCH, M. L. FENSIN, M. R. JAMES, D. B. PELOWITZ, and L. S. WATERS, “MCNPX, Version 2.6.A,” LA-UR-05-8225, Los Alamos National Laboratory (2005).
   Google Scholar
• W. B. WILSON, V. DYADECHKO, T. R. ENGLAND, P. MOLLER, and H. R. TRELLUE, “A Manual for CINDER90 Version 06.1 Codes and Data,” Draft Report, Los Alamos National Laboratory (2006).
   Google Scholar
• G. S. CHANG and J. M. RYSKAMP, “Depletion Analysis of Mixed-Oxide Fuel Pins in Light Water Reactors and the Advanced Test Reactor,” Nucl. Technol., 129, 326 (2000).
   Web of Science ®Google Scholar
• G. S. CHANG, “MCWO-Linking MCNP and ORIGEN2 for Fuel Burnup Analysis,” Proc. Monte Carlo Topl. Mtg., Chattanooga, Tennessee, April 17–21, 2005, American Nuclear Society (2005) (CD-ROM).
   Google Scholar
• N. A HANAN, A. P. OLSON, R. B. POND, and J. E. MATOS, “A Monte Carlo Burnup Code Linking MCNP and REBUS,” ANL-TD-CP-97492, Argonne National Laboratory (1998).
   Google Scholar
• W. HAECK, “An OptimumApproach to Monte Carlo Burn-Up,” PhD Thesis, Ghent University, Belgium (2007).
   Google Scholar
• H. R. TRELLUE and D. I. POSTON, “User’s Manual, Version 2.0 for MONTEBURNS, Version 5B,” LA-UR-99-4999, Los Alamos National Laboratory (1999).
   Google Scholar
• J. CETNAR, W. GUDOWSKI, and J. WALLENIUS, “User Manual for Monte-Carlo Continuous Energy Burnup (MCB) Code—Version 1,” Draft Report, Department of Nuclear and Reactor Physics, Royal Institute of Technology (2005).
   Google Scholar
• D. J. KELLY, “Depletion of a BWR Lattice Using the RACER Continuous Energy Monte Carlo Code,” Proc. Int. Conf. Mathematics and Computation, Reactor Physics, and Environmental Analysis, Portland, Oregon, April 30–May 4, 1995, American Nuclear Society (1995).
   Google Scholar
• C. TIPPAYAKUL, K. IVANOV, and S. MISU, “Improvements of MCOR: New Monte Carlo Depletion Code System for Fuel Assembly Reference Calculations,” Proc. Topl. Mtg. Reactor Physics (PHYSOR 2006), Vancouver, Canada, September 10–14, 2006, American Nuclear Society (2006) (CD-ROM).
   Google Scholar
• K. SUYAMA, H. MOCHIZUKI, and T. KIYOSUMI, “Revised Burnup Code System SWAT: Description and Validation Using Postirradiation Examination Data,” Nucl. Technol., 138, 97 (2002).
   Web of Science ®Google Scholar
• M. EDENIUS, K. EKBERG, B. H. FORSSEN, and D. KNOTT, “CASMO-4, A Fuel Assembly Burnup Program, User’s Manual,” Studsvik/SOA-95/15, Studsvik of America (1995).
   Google Scholar
• N. SUGIMURA, A. YAMAMOTO, T. USHIO, M. MORI, M. TABUCHI, and T. ENDO, “Neutron Transport Models of AEGIS: An Advanced Next-Generation Neutronics Design System,” Nucl. Sci. Eng., 155, 276 (2007).
   Web of Science ®Google Scholar
• D. KNOTT and E. WEHLAGE, “Description of the LANCER02 Lattice Physics Code for Single-Assembly and Multibundle Analysis,” Nucl. Sci. Eng., 155, 331 (2007).
   Web of Science ®Google Scholar
• “HELIOS 1.7 Methods Documentation,” Studsvik Scandpower, Norway (2000).
   Google Scholar
• E. E. LEWIS and W. F. MILLER, Jr., Computational Methods of Neutron Transport, Chap. 7, American Nuclear Society, La Grange Park, Illinois (1993).
   Google Scholar
• H. C. HURIA and R. J. BUECHEL, “Recent Improvements and New Features in the Westinghouse Lattice Physics Codes,” Trans. Am. Nucl. Soc., 72, 369 (1995).
   Google Scholar
• T. P. SHANNON, J. K. WHEELER, and G. TOUVANNAS, “TGBLA0PANACEA and CASMO/MICROBURN Analyses of GE9B/GE10 Fuel in the Quad Cities,” Trans. Am. Nucl. Soc., 74, 287 (1996).
   Google Scholar
• J. S. HENDRICKS, G. W. McKINNEY, M. L. FENSIN, M. R. JAMES, R. C. JOHNS, J. W. DURKEE, J. P. FINCH, D. B. PELOWITZ, L. S. WATERS, and F. X. GALLMEIER, “MCNPX Version 2.6.F,” Draft Report, Los Alamos National Laboratory (2007).
   Google Scholar
• Z. XU, “Design Strategies for Optimizing High Burnup Fuel in Pressurized Water Reactors,” PhD Thesis, Massachusetts Institute of Technology (2003).
   Google Scholar
• J. S. HENDRICKS, G. W. McKINNEY, H. R. TRELLUE, J. W. DURKEE, J. P. FINCH, M. L. FENSIN, M. R. JAMES, D. B. PELOWITZ, L. S. WATERS, F. X. GALLMEIER, and J.-C. DAVID, “MCNPX, Version 2.6.B,” LA-UR-06-3248, Los Alamos National Laboratory (2006).
   Google Scholar
• G. W. McKINNEY and H. R. TRELLUE, “Transmutation Feature Within MCNPX,” LA-UR-04-1572, Los Alamos National Laboratory (2004).
   Google Scholar
• “MCNPX User’s ManualVersion 2.6.0,” LA-CP-07-1473, D. PELOWITZ, Ed., Los Alamos National Laboratory (2008).
   Google Scholar
• W. B. WILSON, T. R. ENGLAND, E. D. ARTHUR, C. A. BEARD, C. D. BOWMAN, L. N. ENGEL, A. GAVRON, D. C. GEORGE. L. DAEMEN, H. G. HUGHES III, W. W. KINNISON, R. J. LABAUVE, D. M. LEE, H. LICHTENSTEIN, P. W. LISOWSKI, D. W. MUIR, A. P. MUIR, A. P. PALOUNEK, R. T. PERRY, E. J. PITCHER, R. E. PRAEL, R. J. RUSSEL, G. SANDERS, L. S. WATERS, P. G. YOUNG, and J. J. ZIOCK, “AcceleratorTransmutation Studies at LosAlamos with LAHET, MCNPX and CINDER90,” Proc. Workshop Simulation of Accelerator Radiation Environments, Santa Fe, New Mexico, January 11–15, 1993 (1993).
   Google Scholar
• J. S. HENDRICKS, G. W. McKINNEY, J. W. DURKEE, J. P. FINCH, M. L. FENSIN, M. R. JAMES, R. C. JOHNS, D. B. PELOWITZ, L. S. WATERS, and F. X. GALLMEIER, “MCNPX, Version 2.6.C,” LA-UR-06-7991, Los Alamos National Laboratory (2006).
   Google Scholar
• J. S. HENDRICKS, G. W. McKINNEY, M. L. FENSIN, M. R. JAMES, R. C. JOHNS, J. W. DURKEE, J. P. FINCH, D. B. PELOWITZ, L. S. WATERS, and F. X. GALLMEIER, “MCNPX, Version 2.6.D,” LA-UR-07-4137, Los Alamos National Laboratory (2007).
   Google Scholar
• J. S. HENDRICKS, G. W. McKINNEY, M. L. FENSIN, M. R. JAMES, R. C. JOHNS, J. W. DURKEE, J. P. FINCH, D. B. PELOWITZ, L. S. WATERS, and F. X. GALLMEIER, “MCNPX Version 2.6.E,” LA-UR-07-6632, Los Alamos National Laboratory (2007).
   Google Scholar
• M. L. FENSIN, J. S. HENDRICKS, G. W. McKINNEY, and H. R. TRELLUE, “Advances in Monte Carlo Depletion Capabilities For MCNPX,” Proc. 14th Biennial Topl. Mtg. Radiation Protection and Shielding Division, Carlsbad, New Mexico, April 2–6, 2006, American Nuclear Society (2006) (CDROM).
   Google Scholar
• M. L. FENSIN, J. S. HENDRICKS, and S. ANGHAIE, “Improved Reaction Rate Tracking and Fission Product Yield Determinations for the Monte Carlo–Linked Depletion Capability in MCNPX,” Nucl. Technol., 164, 3 (2008).
   Web of Science ®Google Scholar
• M. L. FENSIN, J. S. HENDRICKS, H. R. TRELLUE, and S. ANGHAIE, “Incorporation of a Predictor-Corrector Methodology and 1-Group Reaction Rate Reporting Scheme for the MCNPX Depletion Capability,” Trans. Am. Nucl. Soc., 95, 317 (2006).
   Google Scholar
• O. W. HERMANN, S. M. BOWMAN, M. C. BRADY, and C. V. PARKS, “Validation of the SCALE System for PWR Spent Fuel Isotopic Composition Analysis,” ORNL/TM-12667, Oak Ridge National Laboratory (1995).
   Google Scholar
• O. W. HERMANN and C. V. PARKS, “SAS2H:ACoupled One-Dimensional Depletion and Shielding Analysis Module,” in “SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation,” Vol. 1, Sec. S2, NUREG/CR-0200, Rev. 5, ORNL/NUREG/CSD-2R5, Oak Ridge National Laboratory (1997).
   Google Scholar
• A. G. CROFF, “ORIGEN2—A Revised and Updated Version of the Oak Ridge Isotope Generation and Depletion Code,” ORNL-5621, Oak Ridge National Laboratory (1980).
   Google Scholar
• D. B. PELOWITZ, J. S. HENDRICKS, J. W. DURKEE, M. R. JAMES, M. L. FENSIN, G. W. McKINNEY, S. G. MASHNIK, and L. S. WATERS, “MCNPX 2.7.A Extensions,” LAUR-08-07182, Los Alamos National Laboratory (2008).
   Google Scholar
• C. TIPPAYAKUL, M. AVRAMOVA, F. ESPEL, and K. IVANOV, “Investigations on Monte Carlo Based Coupled Core Calculations,” Proc. Int. Congress Advances in Nuclear Power Plants (ICAPP’07), Nice, France, May 13–18, 2007 (2007).
   Google Scholar
• T. TAKEDA, N HIROKAWA, and T. NODA, “Estimate of Error Propagation in Monte-Carlo Burnup Calculations,” J. Nucl. Sci. Technol., 36, 9, 738 (1999).
   Web of Science ®Google Scholar