Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT

Collins, Benjamin; Stimpson, Shane; Kelley, Blake W.; Young, Mitchell T. H.; Kochunas, Brendan; Graham, Aaron; Larsen, Edward W.; Downar, Thomas; Godfrey, Andrew

doi:10.1016/j.jcp.2016.08.022

Title: Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT

Journal Article · Thu Aug 25 00:00:00 EDT 2016 · Journal of Computational Physics

DOI:https://doi.org/10.1016/j.jcp.2016.08.022· OSTI ID:1326469

^[1]; Stimpson, Shane ^[1];

^[2]; Young, Mitchell T. H. ^[2];

^[2];

^[2]; Larsen, Edward W. ^[2]; Downar, Thomas ^[2]; Godfrey, Andrew ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences

We derived a consistent “2D/1D” neutron transport method from the 3D Boltzmann transport equation, to calculate fuel-pin-resolved neutron fluxes for realistic full-core Pressurized Water Reactor (PWR) problems. The 2D/1D method employs the Method of Characteristics to discretize the radial variables and a lower order transport solution to discretize the axial variable. Our paper describes the theory of the 2D/1D method and its implementation in the MPACT code, which has become the whole-core deterministic neutron transport solver for the Consortium for Advanced Simulations of Light Water Reactors (CASL) core simulator VERA-CS. We also performed several applications on both leadership-class and industry-class computing clusters. Results are presented for whole-core solutions of the Watts Bar Nuclear Power Station Unit 1 and compared to both continuous-energy Monte Carlo results and plant data.

View Accepted Manuscript (DOE)

View Accepted Manuscript (Publisher)

Cite

Export

Save

Research Organization:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility (OLCF); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Consortium for Advanced Simulation of LWRs (CASL)

Sponsoring Organization:: USDOE Office of Science (SC)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1326469

Alternate ID(s):: OSTI ID: 1359305

Journal Information:: Journal of Computational Physics, Vol. 326, Issue C; ISSN 0021-9991

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

Citation Metrics:

Cited by: 69 works

Citation information provided by
Web of Science

References (12)

Denovo: A New Three-Dimensional Parallel Discrete Ordinates Code in SCALE Evans, Thomas M.; Stafford, Alissa S.; Slaybaugh, Rachel N. Nuclear Technology, Vol. 171, Issue 2 https://doi.org/10.13182/NT171-171	journal	August 2010
Implementation, capabilities, and benchmarking of Shift, a massively parallel Monte Carlo radiation transport code Pandya, Tara M.; Johnson, Seth R.; Evans, Thomas M. Journal of Computational Physics, Vol. 308 https://doi.org/10.1016/j.jcp.2015.12.037	journal	March 2016
Apollo2 year 2010 Sanchez, Richard; Zmijarevi, Igor; Coste-Delclaux, M. Nuclear Engineering and Technology, Vol. 42, Issue 5 https://doi.org/10.5516/NET.2010.42.5.474	journal	October 2010
Assembly homogenization techniques for light water reactor analysis Smith, K. S. Progress in Nuclear Energy, Vol. 17, Issue 3 https://doi.org/10.1016/0149-1970(86)90035-1	journal	January 1986
A new characteristics algorithm for 3D transport calculations Wu, G. J.; Roy, R. Annals of Nuclear Energy, Vol. 30, Issue 1 https://doi.org/10.1016/S0306-4549(02)00046-4	journal	January 2003
Solution of the C5G7MOX benchmark three-dimensional extension problems by the DeCART direct whole core calculation code Cho, Jin Young; Joo, Han Gyu Progress in Nuclear Energy, Vol. 48, Issue 5 https://doi.org/10.1016/j.pnucene.2006.01.006	journal	July 2006
Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers Jung, Yeon Sang; Shim, Cheon Bo; Lim, Chang Hyun Annals of Nuclear Energy, Vol. 62 https://doi.org/10.1016/j.anucene.2013.06.031	journal	December 2013
High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor Weber, David P.; Sofu, Tanju; Yang, Won Sik Nuclear Science and Engineering, Vol. 155, Issue 3 https://doi.org/10.13182/NSE07-A2672	journal	March 2007
A consistent 2D/1D approximation to the 3D neutron transport equation Kelley, Blake W.; Larsen, Edward W. Nuclear Engineering and Design, Vol. 295 https://doi.org/10.1016/j.nucengdes.2015.07.026	journal	December 2015
Derivation of Optimum Polar Angle Quadrature Set for the Method of Characteristics Based on Approximation Error for the Bickley Function Yamamoto, Akio; Tabuchi, Masato; Sugimura, Naoki Journal of Nuclear Science and Technology, Vol. 44, Issue 2 https://doi.org/10.1080/18811248.2007.9711266	journal	February 2007
Diffusion theory methods for spatial kinetics calculations Sutton, T. M.; Aviles, B. N. Progress in Nuclear Energy, Vol. 30, Issue 2 https://doi.org/10.1016/0149-1970(95)00082-U	journal	January 1996
Monte Carlo Criticality Methods and Analysis Capabilities in SCALE Goluoglu, Sedat; Petrie, Lester M.; Dunn, Michael E. Nuclear Technology, Vol. 174, Issue 2 https://doi.org/10.13182/NT10-124	journal	May 2011

Cited By (7)

Consistent pCMFD Acceleration Schemes of the Three-Dimensional Transport Code PROTEUS-MOC Zhang, Guangchun; Hsieh, Albert; Yang, Won Sik Nuclear Science and Engineering, Vol. 193, Issue 8 https://doi.org/10.1080/00295639.2018.1560854	journal	February 2019
The Subray Method of Characteristics Graham, Aaron M.; Collins, Benjamin S.; Downar, Thomas J. Nuclear Science and Engineering, Vol. 193, Issue 6 https://doi.org/10.1080/00295639.2018.1550988	journal	January 2019
A 2D/1D Algorithm for Effective Cross-Section Generation in Fast Reactor Neutronic Transport Calculations Faure, Bastien; Archier, Pascal; Vidal, Jean-François Nuclear Science and Engineering, Vol. 192, Issue 1 https://doi.org/10.1080/00295639.2018.1480190	journal	July 2018
The RAPID Fission Matrix Approach to Reactor Core Criticality Calculations Walters, William J.; Roskoff, Nathan J.; Haghighat, Alireza Nuclear Science and Engineering, Vol. 192, Issue 1 https://doi.org/10.1080/00295639.2018.1497395	journal	July 2018
Improved Accuracy in the 2-D/1-D Method with Anisotropic Transverse Leakage and Cross-Section Homogenization Jarrett, Michael; Kochunas, Brendan; Larsen, Edward Nuclear Science and Engineering, Vol. 192, Issue 3 https://doi.org/10.1080/00295639.2018.1507186	journal	September 2018
Polar Parity for Efficient Evaluation of Anisotropic Transverse Leakage in the 2D/1D Transport Method Jarrett, Michael; Kochunas, Brendan; Larsen, Edward Nuclear Science and Engineering, Vol. 193, Issue 12 https://doi.org/10.1080/00295639.2019.1627176	journal	July 2019
Quasi-Diffusion Method with 3-D Cross Sections for TREAT Core Analysis Xu, Yunlin; Seker, Volkan; Downar, Thomas J. Nuclear Technology, Vol. 206, Issue 6 https://doi.org/10.1080/00295450.2019.1672451	journal	December 2019

Similar Records

Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT

Journal Article · Thu Dec 01 00:00:00 EST 2016 · Journal of Computational Physics · OSTI ID:1326469

Collins, Benjamin; Stimpson, Shane; Kochunas, Brendan; +3 more

Advanced Nodal P₃/SP₃ Axial Transport Solvers for the MPACT 2D/1D Scheme

Conference · Thu Jan 01 00:00:00 EST 2015 · OSTI ID:1326469

Stimpson, Shane G; Collins, Benjamin S

Flexible Spatial Partitions in MPACT Through Module-Based Data Passing

Journal Article · Sat Jul 01 00:00:00 EDT 2017 · Transactions of the American Nuclear Society · OSTI ID:1326469

Stimpson, Shane; Collins, Benjamin

Related Subjects

97 MATHEMATICS AND COMPUTING
71 CLASSICAL AND QUANTUM MECHANICS
GENERAL PHYSICS
2D/1D method
MOC
MPACT

Title: Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT

Citation Formats

References (12)

Cited By (7)

Similar Records

Related Subjects