APOLLO3®: Overview of the new code capabilities for reactor physics analysis
P Mosca, L Bourhrara, A Calloo… - Nuclear Science and …, 2024 - Taylor & Francis
APOLLO3® is a French deterministic reactor code for lattice and core calculations. It has
been developed at CEA (Commissariat à l'Energie Atomique) with the financial and …
been developed at CEA (Commissariat à l'Energie Atomique) with the financial and …
Method of characteristics for 3D, full-core neutron transport on unstructured mesh
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 …
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 …
Characteristics (MOC) solver of the APOLLO3® code, with the aim of applying the method to …
Improvement of the 3D MOC/DD neutron transport method with thin axial meshes
M Dai, A Zhang, M Cheng - Annals of Nuclear Energy, 2023 - Elsevier
Significant accuracy loss has been observed in the MOC/DD method using thin axial
meshes. A theoretical analysis indicates that the accuracy loss results from the deviation in …
meshes. A theoretical analysis indicates that the accuracy loss results from the deviation in …
[HTML][HTML] An efficient heterogeneous parallel algorithm of the 3D MOC for multizone heterogeneous systems
Recent innovations in powerful high-performance computing (HPC) architecture have
enabled high-fidelity whole-core neutron transport simulations in a reasonable amount of …
enabled high-fidelity whole-core neutron transport simulations in a reasonable amount of …
Numerical optimization of a multiphysics calculation scheme based on partial convergence
P Cattaneo, R Lenain, E Merle, C Patricot… - Annals of Nuclear …, 2021 - Elsevier
This paper deals with the numerical optimization of a multiphysics calculation scheme. The
purpose of this tool is the fine-scale neutronic and thermal-hydraulic modelling of …
purpose of this tool is the fine-scale neutronic and thermal-hydraulic modelling of …
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 …
examine when considering any transport discretization. In the past, particle conservation has …
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 …
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
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 …
the definition of homogenized and energy-collapsed cross sections. In modern sodium fast …
Time-dependent neutron transport method based on three-dimensional method of characteristics
Q Song, C Zhang, Y Wu, K Feng, H Guo, H Gu - Annals of Nuclear Energy, 2024 - Elsevier
Abstract The 3D Method of Characteristics (MOC) has high numerical accuracy, geometrical
flexibility, making it suitable for the simulation of advanced reactors with complex geometry …
flexibility, making it suitable for the simulation of advanced reactors with complex geometry …