Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT
- Oak Ridge National Laboratory, One Bethel Valley Rd., Oak Ridge, TN 37831 (United States)
- Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109 (United States)
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
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Related Subjects
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