An improved MCNP-ORIGEN depletion program (MCODE) and its verification for high-burnup applications

Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting

Volumn , Issue , 2002, Pages

  Xu, Zhiwen ^a   Hejzlar, Pavel ^a   Driscoll, Michael J ^a   Kazimi, Mujid S ^a  

^a Massachusetts Institute of Technology Cambridge   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

APPLICATION PROGRAMS; EIGENVALUES AND EIGENFUNCTIONS; FAST REACTORS; ISOTOPES; MONTE CARLO METHODS; OXIDE MINERALS; REACTOR CORES; THORIA; URANIUM DIOXIDE;

AUTOMATIC GENERATION; CONTINUOUS ENERGY MONTE CARLO CODE; DEPLETION CALCULATION; ISOTOPIC COMPOSITION; LATTICE CONFIGURATION; MATERIAL COMPOSITIONS; MONTE CARLO APPROACH; PREDICTOR-CORRECTOR ALGORITHM;

PRESSURIZED WATER REACTORS;

EID: 2642564888     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (13)

1. Judith F. Briesmeister (editor), “MCNPTM - A General Monte Carlo N-Particle Transport Code, Version 4C,” LA-13709-M, Los Alamos National Laboratory (April 2000).
2. Allen G. Croff, “A User's Manual for the ORIGEN2 Computer Code,” ORNL/TM-7175, Oak Ridge National Laboratory (July 1980).
3. R.L. Moore, B.G. Schnitzler, C.A. Wemple, R.S. Babcock, D.E. Wessol, “MOCUP: MCNPORIGEN2 Coupled Utility Program,” INEL-95/0523, Idaho National Engineering Laboratory (September 1995).
4. David I. Poston, Holly R. Trellue, “User's Manual, Version 2.0, for Monteburns, Version 1.0,” LA-UR-99-4999, Los Alamos National Laboratory (September 1999).
5. Keisuke Okumura, Takamasa Mori, Masayuki Nakagawa, Kunio Kaneko, “Validation of a Continuous-Energy Monte Carlo Burn-up Code MVP-BURN and Its Application to Analysis of Post Irradiation Experiment,” Journal of Nuclear Science and Technology, Vol 37, No 2, pp 128-138 (February 2000).
6. Jerzy Cetnar, Waclaw Gudowski, Jan Wallenius, Kamil Tucek, “Simulation of Nuclide Transmutations with Monte-Carlo Continuous Energy Burnup Code (MCB1C),” Embedded ANS Topical Meeting of Accelerator Applications/Accelerator Driven Transmutation Technology and Application (AccApp/ADTTA'01), Reno, NV (November 11-15, 2001).
7. M.D. DeHart, M.C. Brady, C.V. Parks, “OECD/NEA Burnup Credit Calculational Criticality Benchmark Phase 1-B Results,” ORNL-6901, Oak Ridge National Laboratory (June 1996).
8. Xianfeng Zhao, M.J. Driscoll, M.S. Kazimi, “Micro-Heterogeneous Thorium Based Fuel Concepts for Pressurized Water Reactors,” MIT-NFC-TR-031 (August 2001).
9. Allen G. Croff, “ORIGEN2: A Versatile Computer Code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials,” Nuclear Technology, Vol 62, pp 335-352 (September 1983).
10. P.J. Finck, R.N. Blomquist, C.G. Stenberg, C. Jammes, “Evaluation of Fission Product Worth Margins in PWR Spent Nuclear Fuel Burnup Credit Calculations,” ANL-FRA-1998-1, Argonne National Laboratory (1998).
11. Xianfeng Zhao, Pavel Hejzlar, M.J. Driscoll, “Comparison of Code Results for PWR Thorium/Uranium Pin Cell Burnup,” MIT-NFC-TR-027, Center for Advanced Nuclear Energy Systems, MIT (November 2000).
12. C.M. Kang, R.O. Mosteller, “Incorporation of a Predictor-Corrector Depletion Capability into the CELL-2 Code,” Transaction of American Nuclear Society, Vol 45, pp 729-731 (1983).
13. Malte Edenius, Kim Ekberg, Bengt H. Forssen, Dave Knott, “CASMO-4, A Fuel Assembly Burnup Program, User's Manual,” Studsvik/SOA-95/1, Studsvik of America, Inc. (1995).