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

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.
Authors:
ORCiD logo [1] ;  [1] ; ORCiD logo [2] ;  [2] ; ORCiD logo [2] ; ORCiD logo [2] ;  [2] ;  [2] ;  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences
Publication Date:
Grant/Contract Number:
AC05-00OR22725
Type:
Accepted Manuscript
Journal Name:
Journal of Computational Physics
Additional Journal Information:
Journal Volume: 326; Journal Issue: C; Journal ID: ISSN 0021-9991
Publisher:
Elsevier
Research Org:
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 Org:
USDOE Office of Science (SC)
Country of Publication:
United States
Language:
English
Subject:
97 MATHEMATICS AND COMPUTING; 71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS; 2D/1D method; MOC; MPACT
OSTI Identifier:
1326469
Alternate Identifier(s):
OSTI ID: 1359305

Collins, Benjamin, Stimpson, Shane, Kelley, Blake W., Young, Mitchell T. H., Kochunas, Brendan, Graham, Aaron, Larsen, Edward W., Downar, Thomas, and Godfrey, Andrew. Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT. United States: N. p., Web. doi:10.1016/j.jcp.2016.08.022.
Collins, Benjamin, Stimpson, Shane, Kelley, Blake W., Young, Mitchell T. H., Kochunas, Brendan, Graham, Aaron, Larsen, Edward W., Downar, Thomas, & Godfrey, Andrew. Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT. United States. doi:10.1016/j.jcp.2016.08.022.
Collins, Benjamin, Stimpson, Shane, Kelley, Blake W., Young, Mitchell T. H., Kochunas, Brendan, Graham, Aaron, Larsen, Edward W., Downar, Thomas, and Godfrey, Andrew. 2016. "Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT". United States. doi:10.1016/j.jcp.2016.08.022. https://www.osti.gov/servlets/purl/1326469.
@article{osti_1326469,
title = {Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT},
author = {Collins, Benjamin and Stimpson, Shane and Kelley, Blake W. and Young, Mitchell T. H. and Kochunas, Brendan and Graham, Aaron and Larsen, Edward W. and Downar, Thomas and Godfrey, Andrew},
abstractNote = {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.},
doi = {10.1016/j.jcp.2016.08.022},
journal = {Journal of Computational Physics},
number = C,
volume = 326,
place = {United States},
year = {2016},
month = {8}
}