Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
4967889 | Journal of Computational Physics | 2016 | 17 Pages |
Abstract
A consistent ā2D/1Dā 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.
Related Topics
Physical Sciences and Engineering
Computer Science
Computer Science Applications
Authors
Benjamin Collins, Shane Stimpson, Blake W. Kelley, Mitchell T.H. Young, Brendan Kochunas, Aaron Graham, Edward W. Larsen, Thomas Downar, Andrew Godfrey,