Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations
Author:
Affiliation:
1. University of Michigan, 2355 Bonisteel Boulevard, Ann Arbor, Michigan 48109
Funder
U.S. Department of Energy
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2023.2224234
Reference50 articles.
1. J. R. ASKEW, “A Characteristics Formulation of the Neutron Transport Equation in Complicated Geometries,” AEEW-M–1108. United Kingdom Atomic Energy Authority (1972).
2. MPACT TEAM, “MPACT Theory Manual, Version 2.2.0,” ORNL/TM-2016/476, Consortium for Advanced Simulation of Light Water Reactors (2016).
3. VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion
4. Transport Calculations of MOX and UO2Pin Cells by the Method of Characteristics
5. A Linear Surface Characteristics Approximation for Neutron Transport in Unstructured Meshes
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