Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations

Author:

Choi Sooyoung1ORCID,Fitzgerald Andrew1ORCID,Herring Nicholas1ORCID,Kochunas Brendan1ORCID

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

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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