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

Journal Article · · Journal of Computational Physics
 [1];  [1];  [2];  [2];  [2];  [1]
  1. Oak Ridge National Laboratory, One Bethel Valley Rd., Oak Ridge, TN 37831 (United States)
  2. Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109 (United States)
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A consistent “2D/1D” neutron transport method is derived 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. This 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. Several applications have been performed 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.

OSTI ID:
22622218
Journal Information:
Journal of Computational Physics, Vol. 326; Other Information: Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA); ISSN 0021-9991
Country of Publication:
United States
Language:
English

Cited By (7)

Quasi-Diffusion Method with 3-D Cross Sections for TREAT Core Analysis journal December 2019
A 2D/1D Algorithm for Effective Cross-Section Generation in Fast Reactor Neutronic Transport Calculations journal July 2018
The RAPID Fission Matrix Approach to Reactor Core Criticality Calculations journal July 2018
Improved Accuracy in the 2-D/1-D Method with Anisotropic Transverse Leakage and Cross-Section Homogenization journal September 2018
The Subray Method of Characteristics journal January 2019
Consistent pCMFD Acceleration Schemes of the Three-Dimensional Transport Code PROTEUS-MOC journal February 2019
Polar Parity for Efficient Evaluation of Anisotropic Transverse Leakage in the 2D/1D Transport Method journal July 2019

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Related Subjects

75 CONDENSED MATTER PHYSICS
SUPERCONDUCTIVITY AND SUPERFLUIDITY
97 MATHEMATICAL METHODS AND COMPUTING
ACCURACY
BOLTZMANN EQUATION
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
FUEL PINS
FUELS
MATHEMATICAL SOLUTIONS
MONTE CARLO METHOD
NEUTRON FLUX
NEUTRON TRANSPORT
NUCLEAR POWER
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
SIMULATORS
STABILITY