Method of characteristics for 3D, full-core neutron transport on unstructured mesh

DR Gaston, B Forget, KS Smith, LH Harbour… - Nuclear …, 2021 - Taylor & Francis
A myriad of nuclear reactor designs are currently being considered for next-generation
power production. These designs utilize unique geometries and materials and can rely on …

Cross sections polynomial axial expansion within the APOLLO3® 3D characteristics method

A Gammicchia, S Santandrea, S Dulla - Annals of Nuclear Energy, 2022 - Elsevier
A polynomial expansion for cross sections has been introduced in the 3D Method Of
Characteristics (MOC) solver of the APOLLO3® code, with the aim of applying the method to …

Consistent pCMFD acceleration schemes of the three-dimensional transport code PROTEUS-MOC

G Zhang, A Hsieh, WS Yang… - Nuclear Science and …, 2019 - Taylor & Francis
This paper presents the new acceleration schemes implemented in the three-dimensional (3-
D) transport solver PROTEUS-MOC in conjunction with the fixed-point iteration (FPI) …

Accelerated polynomial axial expansions for full 3D neutron transport MOC in the APOLLO3® code system as applied to the ASTRID fast breeder reactor

S Santandrea, L Graziano, D Sciannandrone - Annals of Nuclear Energy, 2018 - Elsevier
In recent years a solver based on the Method of Characteristics (MOC) allowing the
treatment of 3D extruded geometries has been developed inside the TDT code of APOLLO3 …

The linear source approximation and particle conservation in the Method of Characteristics for isotropic and anisotropic sources

RM Ferrer, JD Rhodes III - Annals of Nuclear Energy, 2018 - Elsevier
Particle conservation, otherwise known as particle balance, is one of the main properties to
examine when considering any transport discretization. In the past, particle conservation has …

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

S Choi, A Fitzgerald, N Herring… - Nuclear Science and …, 2024 - Taylor & Francis
This work seeks to improve upon an existing formulation of the Method of Characteristics
(MOC) with a Linear Source Approximation (LSA) for problems that use nonconstant cross …

Parallel, asynchronous ray-tracing for scalable, 3D, full-core method of characteristics neutron transport on unstructured mesh

DR Gaston - 2020 - dspace.mit.edu
Several key issues have hindered these attempts: lack of fuel volume preservation,
approximations of boundary conditions, inefficient spatial domain decompositions …

A MOC-based neutron kinetics model for noise analysis

A Gammicchia, S Santandrea, I Zmijarevic… - Annals of Nuclear …, 2020 - Elsevier
A 2-D noise model is implemented in the deterministic reactor code APOLLO3® to simulate
a periodic oscillation of a structural component. The Two/Three Dimensional Transport …

Application of the SPH method to account for the angular dependence of multigroup resonant cross sections in thermal reactor calculations

L Mao, I Zmijarevic, K Routsonis - Annals of Nuclear Energy, 2019 - Elsevier
The issue of the angular dependence of the multigroup total cross sections in the multigroup
transport equation solution was recognized a long time ago. Only recently has its impact on …

3D heterogeneous Cartesian cells for transport-based core simulations

E Masiello, R Lenain, W Ford - Annals of Nuclear Energy, 2020 - Elsevier
We present in this paper a discrete-ordinates transport method to perform 3D PWR transport
simulations. The numerical technique takes profit of the Cartesian modular construction of …