Keywords
BWR
Nuclear core design
Steady-state
Nuclear core design
Steady-state
Abstract
An overview on nuclear methods for boiling water reactors (BWR) core design and analysis is provided based on the ANS Standard 19.3. The steady-state BWR nuclear methods, composed of neutron cross section library generation method, lattice physics method and core physics method, are systematically reviewed and associated computer codes in common use for BWR core design and analysis are listed. Veri?cation and validation, the two complementary aspects in determining the range of applicability of the calculation system, are discussed extensively. The biases and uncertainties for the predictions from the calculation system over its demonstrated range of applicability are also discussed.
References
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American Nuclear Society. 2013b. ANS 19.3:2011(R2017):Steady-State Neutronics Methods for Power Reactor Analysis. American Nuclear Society.
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Downar T, Yu X, Seker V. 2009. PARCS v3.0 Theory Manual.Technical report. University of Michigan. Ann Arbor.
Dunn M, Greene M. 2002. Cross-section processing system for generating nuclear data for criticality safety appli- cations. Trans Am Nucl Soc 86:118–119.
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Knott D, Wehlage E. 2007. Description of the LANCR02 lat-tice physics code for single-assembly and multi-bundle analysis. Nucl Sci Eng 155(3):331–354. doi:10.13182/ nse155-331.
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Palmtag S, Lamas J, Finch J, Godfrey A, Moore BR. 2008. The advanced BWR core simulator AETNA02.
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Rhoades WA, Childs RL. 1987. The TORT three-dimensional discrete ordinates neutron/photon transport code. Technical Report ORNL-6268. Oak Ridge National Lab.. Oak Ridge.
Rhoades WA, Childs RL. 1988. The DORT two-dimensional discrete ordinates transport code. Nucl Sci Eng 99(1):88–89. doi:10.13182/NSE88-A23547.
Smith KS, Rempe KR, VerPlanck DM. 1989. SIMULATE-3 Methodology: Advanced three-dimensional two group reactor analysis code. Technical report. Studsvik of America, Inc.. Newton [MA].
Stammler R, Olsson S, Bernander ?. 1977. The PHOENIX computer program for fuel assembly and pin cell calcu- lations. Technical Report ASEA ATOM PM RCA 77-012,.
Turinsky P, Al-Chalabi R, Engrand P, Sarsour H, Faure F, Guo W. 2003. NESTLE Version 5.2.1: Few-group neu- tron diffusion equation solver utilizing the nodal ex- pansion method for eigenvalue, adjoint, ?xed-source steady-state and transient problems. Technical report.North Carolina State University. Raleigh. doi:10.2172/ 10191160.
Woolley JA. 1976. Three-dimensional BWR core simulator. Boiling Water Reactor Systems Dept., General Electric Company. X-5 Monte Carlo Team. 2003. MCNP–a general Monte Carlo N-particle transport code, version 5.
Yamamoto M, Ando Y, Unamo T, Mizuta H, Seino H. 1987. Recent developments in TGBLA lattice physics code. In: Proc Int Topl Mtg Advances in Reactor Physics, Mathe- matics, and Computations. volume 3. Paris.
Yamamoto M, Mizuta H, Makino K, Chiang RT. 1984. Devel- opment, and validation of TGBLA BWR lattice physics methods,. In: Proc Topl Mtg on Reactor Physics and Shielding. volume 1. Chicago [IL].
American Nuclear Society. 2013b. ANS 19.3:2011(R2017):Steady-State Neutronics Methods for Power Reactor Analysis. American Nuclear Society.
Askew JR, Fayers FJ, Kemshell PB. 1966. General description of the lattice code WIMS. J Brit Nucl Energy Soc 5:564–585.
Borresen S. 1971. A simpli?ed, coarse mesh, three dimen-sional diffusion scheme for calculating the gross power distribution in a boiling water reactor. Nucl Sci Eng 44:37–44.
Borresen S, Skardhamar T. 1987. Recent developments in the lattice physics code RECORD. volume 3. Paris. Casal J, Stammler R, Villarino E, Ferri AA. 1991. HELIOS: geo-metric capabilities of a new fuel assembly program. In:Proc Int Topl Mtg Advances in Mathematics, Computa- tions, and Reactor Physics. volume 5. Pittsburgh [PA]. p. 13.
Chiang RT, Sitaraman S, Jenkins A, Asano K, Koyabu K. 2001. Development, validation and application of innovativeMNCP-based BWR ?uence computational package MF3D. In: 9th Int Conf on Nuclear Engineering. Nice. p. 8–12.
Cobb WR, Borland RS, Darnell BL, Versteegen PL, Ver Planck DM. 1987. ARMP-02 documentation: Part 2, Chapter 8, SIMULATE-E (Mod. 3) computer code manual. Techni- cal Report EPRI-NP–4574-CCM-PT.2-CH.8. Science Ap- plications.
Crowther R, Congdon S, Crawford B, Kang C, Leonard A, Martin C, McDaniel C, Schwager L, Walter RA. 1981. Three dimensional simulation of large power reactors. In: Proceedings of International Topical Meeting on Ad- vances in Mathematical Methods for the Solution of Nu- clear Engineering Problems. Munich.
DeHart MD. 2006. TRITON: a two-dimensional depletion sequence for characterization of spent nuclear fuel. Technical Report ORNL/TM-2005/39 Version 6, Vols. I-III. Oak Ridge National Laboratory. Oak Ridge.
Downar T, Yu X, Seker V. 2009. PARCS v3.0 Theory Manual.Technical report. University of Michigan. Ann Arbor.
Dunn M, Greene M. 2002. Cross-section processing system for generating nuclear data for criticality safety appli- cations. Trans Am Nucl Soc 86:118–119.
Edenius M, Forssen B, Gragg aC. 1991. The physics model of CASMO 4. In: Proc Int Topl Mtg Advances in Math- ematics, Computations, and Reactor Physics. volume 2. Pittsburgh [PA].
Knott D, Wehlage E. 2007. Description of the LANCR02 lat-tice physics code for single-assembly and multi-bundle analysis. Nucl Sci Eng 155(3):331–354. doi:10.13182/ nse155-331.
Lindelow U, Jonsson C, Lindahl aSO. 1990. The ABB atom PWR core design code package. In: Reactor Core De- sign and Performance Evaluation Methods, ASEA Atom Report RCA. volume 77. Nuremberg. p. 15.
Lindenmeier C, Timmons D, Correll GR. 1988. Advanced methodology for LWR core design. In: Proc. of the 1988 International Reactor Physics Conference. volume 1. Jackson Hole [WY].
MacFarlane RE, Muir DW. 1994. The NJOY nuclear data pro-cessing system Version 91. Technical Report LA–12740- M. Los Alamos National Lab.
Marleau G. 1998. Fine mesh 3-D collision probability cal-culations using the lattice code DRAGON. In: Inter- national Conference on the Physics of Nuclear Science and Technology. Long Island [NY]. p. 523–530.
Palmtag S, Lamas J, Finch J, Godfrey A, Moore BR. 2008. The advanced BWR core simulator AETNA02.
Petrie LM, Landers NF. 2009. KENO V.a: an improved Monte Carlo criticality program with supergrouping. Ver. 6. Technical Report NUREG/CR–0200-VOL.2. OakRidge National Laboratory. Oak Ridge.
Rhoades WA, Childs RL. 1987. The TORT three-dimensional discrete ordinates neutron/photon transport code. Technical Report ORNL-6268. Oak Ridge National Lab.. Oak Ridge.
Rhoades WA, Childs RL. 1988. The DORT two-dimensional discrete ordinates transport code. Nucl Sci Eng 99(1):88–89. doi:10.13182/NSE88-A23547.
Smith KS, Rempe KR, VerPlanck DM. 1989. SIMULATE-3 Methodology: Advanced three-dimensional two group reactor analysis code. Technical report. Studsvik of America, Inc.. Newton [MA].
Stammler R, Olsson S, Bernander ?. 1977. The PHOENIX computer program for fuel assembly and pin cell calcu- lations. Technical Report ASEA ATOM PM RCA 77-012,.
Turinsky P, Al-Chalabi R, Engrand P, Sarsour H, Faure F, Guo W. 2003. NESTLE Version 5.2.1: Few-group neu- tron diffusion equation solver utilizing the nodal ex- pansion method for eigenvalue, adjoint, ?xed-source steady-state and transient problems. Technical report.North Carolina State University. Raleigh. doi:10.2172/ 10191160.
Woolley JA. 1976. Three-dimensional BWR core simulator. Boiling Water Reactor Systems Dept., General Electric Company. X-5 Monte Carlo Team. 2003. MCNP–a general Monte Carlo N-particle transport code, version 5.
Yamamoto M, Ando Y, Unamo T, Mizuta H, Seino H. 1987. Recent developments in TGBLA lattice physics code. In: Proc Int Topl Mtg Advances in Reactor Physics, Mathe- matics, and Computations. volume 3. Paris.
Yamamoto M, Mizuta H, Makino K, Chiang RT. 1984. Devel- opment, and validation of TGBLA BWR lattice physics methods,. In: Proc Topl Mtg on Reactor Physics and Shielding. volume 1. Chicago [IL].
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