TARS: A parallel tetrahedral discontinuous finite element code for the solution of the discrete ordinates neutron transport equation

G Zhang, H Zhang - Annals of Nuclear Energy, 2024 - Elsevier
In this study, we introduce TARS, a neutron transport code based on the discrete-ordinates
discontinuous finite element (SN-DFEM) method, which tackles existing challenges in the …

Kinetic methods in Monte Carlo code RMC and its implementation to C5G7-TD benchmark

X Guo, X Shang, J Song, G Shi, S Huang… - Annals of Nuclear …, 2021 - Elsevier
Reactor safety analyses require high-fidelity numerical solutions of transient neutron
transport problems. A predictor–corrector quasi-static (PCQS) method based on the Monte …

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 …

Quadratic axial expansion function with sub-plane acceleration scheme for the high-fidelity transport code PROTEUS-MOC

G Zhang, WS Yang - Annals of Nuclear Energy, 2020 - Elsevier
PROTEUS-MOC is a pin-resolved high-fidelity transport code that employs the method of
characteristics to discretize the radial variables and the discontinuous finite element method …

A Robust, Relaxation-Free Multiphysics Iteration Scheme for CMFD-Accelerated Neutron Transport k-Eigenvalue Calculations—II: Numerical Results

Q Shen, S Choi, B Kochunas - Nuclear Science and Engineering, 2021 - Taylor & Francis
In a companion paper, we present the theoretical development of a new robust, relaxation-
free iteration scheme for multiphysics k-eigenvalue problems. These types of problems are …

Marvin: A parallel three-dimensional transport code based on the discrete ordinates method for reactor shielding calculations

G Zhang, Z Li - Progress in Nuclear Energy, 2021 - Elsevier
Marvin is a parallel three-dimensional discrete ordinates (SN) code dedicated for reactor
shielding calculations. It employs the multi-group and SN approximations to discretize the …

Development of a GPU-based three-dimensional neutron transport code

A Zhang, M Dai, M Cheng, J Wu, J Chen - Annals of Nuclear Energy, 2022 - Elsevier
A GPU-based three-dimensional (3D) neutron transport code, named ThorMOC, is
developed in this work. A GPU-parallelized transport sweeping algorithm based on a planar …

Stability and Performance of the X-CMFD Method for Multiphysics Reactor Calculations

Q Shen, N Adamowicz, S Choi, Y Liu… - Nuclear Science and …, 2024 - Taylor & Francis
This paper presents an innovative approach to efficiently perform deterministic direct whole-
core transport calculations with multiphysics feedback for steady-state problems …

Consistent transport transient solvers of the high-fidelity transport code PROTEUS-MOC

A Hsieh, G Zhang, WS Yang - Nuclear Science and Engineering, 2020 - Taylor & Francis
This paper presents the three new pin-resolved transient solvers of PROTEUS-MOC
developed in a consistent way to the latest steady-state solver. A new transient fixed source …

Robust and efficient methods in transient whole-core neutron transport calculations

Q Shen - 2021 - deepblue.lib.umich.edu
Modeling the time-dependent transient behavior of nuclear reactors with high-fidelity pin-
resolved detail has increased importance when the operating power of the reactor is …