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Title: Three-Dimensional Full-Core BEAVRS Using OpenMOC with Transport Equivalence

Journal Article · · Nuclear Science and Engineering
ORCiD logo [1];  [2];  [2]
  1. Idaho National Laboratory, Computational Frameworks, 1955 Fremont Avenue, Idaho Falls, Idaho 83415; Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 77 Massachusetts Avenue, Cambridge, Massachusetts 02149
  2. Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 77 Massachusetts Avenue, Cambridge, Massachusetts 02149

Using an optimized implementation of the three-dimensional (3D) method of characteristics for neutron transport, along with a novel equivalence method for transport calculations that was designed to correct self-shielding errors from neglecting the angular dependence of resonant group absorption, a 3D full-core light water reactor hybrid stochastic-deterministic eigenvalue calculation was achieved. This paper presents the optimizations developed and compares the transport solutions obtained. For the statepoint, run times near 10 000 CPU hours are achieved—improving on previous works by an order of magnitude—with near 1% error on pin fission to 238U capture ratios and a few dozen pcms on the eigenvalue.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP); USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF)
Grant/Contract Number:
AC07-05ID14517; NE0008578
OSTI ID:
2352634
Report Number(s):
INL/JOU--23-72565-Rev000
Journal Information:
Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Vol. 2024; ISSN 0029-5639
Publisher:
Taylor & FrancisCopyright Statement
Country of Publication:
United States
Language:
English

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Calculation of multi-group migration areas in deterministic transport simulations journal June 2020
A task-based parallelism and vectorized approach to 3D Method of Characteristics (MOC) reactor simulation for high performance computing architectures journal May 2016
Practical resolution of angle dependency of multigroup resonance cross sections using parametrized spectral superhomogenization factors journal September 2017
Generalized Equivalence Theory Used with Spatially Linear Sources in the Method of Characteristics for Neutron Transport journal May 2020
Flux-Limited Diffusion Theory with Anisotropic Scattering journal April 1984