APOLLO2 year 2010

R Sanchez, I Zmijarevi, M Coste-Delclaux… - Nuclear engineering …, 2010 - koreascience.kr
This paper presents the mostortant developments implemented in the APOLLO2 spectral
code since its last general presentation at the 1999 M&C conference in Madrid. APOLLO2 …

A Hybrid Parallel Algorithm for the 3-D Method of Characteristics Solution of the Boltzmann Transport Equation on High Performance Compute Clusters.

BM Kochunas - 2013 - deepblue.lib.umich.edu
The focus of this thesis is on the development of a highly scalable parallel algorithm for
solving the 3-D method of characteristics (MOC) form of the Boltzmann neutron transport …

A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors

M Dai, M Cheng - Annals of Nuclear Energy, 2024 - Elsevier
The planar method of characteristics (MOC) combined with the coarse-mesh finite difference
(CMFD) method is highly effective for solving the neutron transport equation in pressurized …

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 …

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 …

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 …

Advanced method for neutronic simulation of control rods in sodium fast reactors: numerical and experimental validation

H Guo, E Garcia, B Faure, L Buiron, P Archier… - Annals of Nuclear …, 2019 - Elsevier
High accuracy neutronic simulations are required for the development of Generation-IV
sodium cooled fast reactors (SFR). This paper therefore focuses on the development and …

Neutronic calculation of an axially heterogeneous ASTRID fuel assembly with APOLLO3®: Analysis of biases and foreseen improvements

B Faure, P Archier, JF Vidal, JM Palau, L Buiron - Annals of Nuclear Energy, 2018 - Elsevier
Abstract Design of modern sodium fast reactors such as the French SFR project ASTRID are
axially heterogeneous in order to maximize neutron leakage and therefore improve their …

A Novel High-Order Surface Characteristics Scheme for the Neutron Transport Equation in 2D Unstructured Meshes

M Tiberga, S Santandrea - Nuclear Science and Engineering, 2024 - Taylor & Francis
The development of higher-order method of characteristics (MOC) discretizations has
become of great interest to improve the performance of solvers based on the standard …

A 2D/1D algorithm for effective cross-section generation in fast reactor neutronic transport calculations

B Faure, P Archier, JF Vidal, L Buiron - Nuclear Science and …, 2018 - Taylor & Francis
Fast resolution of the Boltzmann transport equation over a nuclear reactor core presupposes
the definition of homogenized and energy-collapsed cross sections. In modern sodium fast …