[HTML][HTML] APOLLO3 homogenization techniques for transport core calculations—application to the ASTRID CFV core

JF Vidal, P Archier, B Faure, V Jouault, JM Palau… - Nuclear Engineering …, 2017 - Elsevier
This paper presents a comparison of homogenization techniques implemented in the
APOLLO3 platform for transport core calculations: standard scalar flux weighting and new …

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 …

ANT-MOC: Scalable Neutral Particle Transport Using 3D Method of Characteristics on Multi-GPU Systems

S Li, Z Wang, L Bu, J Wang, Z Xin, S Li… - Proceedings of the …, 2023 - dl.acm.org
The Method Of Characteristic (MOC) to solve the Neutron Transport Equation (NTE) is the
core of full-core simulation for reactors. High resolution is enabled by discretizing the NTE …

A neutron transport characteristics method for 3D axially extruded geometries coupled with a fine group self-shielding environment

S Santandrea, D Sciannandrone… - Nuclear Science and …, 2017 - Taylor & Francis
In this paper we describe some recent developments in the Method of Characteristics (MOC)
for three-dimensional (3D) extruded geometries in the nuclear reactor analysis code …

ARCHER-a new Three-Dimensional method of characteristics neutron transport code for Pebble-bed HTR with coarse mesh finite difference acceleration

K Zhu, B Kong, J Hou, H Zhang, J Guo, F Li - Annals of Nuclear Energy, 2022 - Elsevier
A new deterministic code ARCHER using Three-Dimensional (3-D) Method of
Characteristics (MOC) has been developed by Institute of Nuclear and new Energy …

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 …

[HTML][HTML] Optimization of reactivity control in a small modular sodium-cooled fast reactor

H Guo, L Buiron, P Sciora, T Kooyman - Nuclear Engineering and …, 2020 - Elsevier
The small modular sodium-cooled fast reactor (SMSFR) is an important component of
Generation-IV reactors. The objective of this work is to improve the reactivity control in …

The Random Ray Method for neutral particle transport

JR Tramm, KS Smith, B Forget, AR Siegel - Journal of Computational …, 2017 - Elsevier
A new approach to solving partial differential equations (PDEs) based on the method of
characteristics (MOC) is presented. The Random Ray Method (TRRM) uses a stochastic …

Optimized control rod designs for Generation-IV fast reactors using alternative absorbers and moderators

H Guo, L Buiron, T Kooyman, P Sciora - Annals of Nuclear Energy, 2019 - Elsevier
The characteristics of Generation-IV fast reactors strongly impact the design of its control
rods. The traditional control rod is a cluster of vented pins with boron carbide (B 4 C) as the …

High-Fidelity Neutron Transport Solution of High Temperature Gas-Cooled Reactor by Three-Dimensional Linear Source Method of Characteristics

K Zhu, B Kong, H Zhang, J Guo, F Li - Nuclear Science and …, 2023 - Taylor & Francis
Recently, a three-dimensional method of characteristics (MOC) code called Advanced
Reactor CHaracteristics tracER (ARCHER) has been developed by the Institute of Nuclear …