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 …

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 …

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 …

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 …

Recent innovations in powerful high-performance computing (HPC) architecture have
enabled high-fidelity whole-core neutron transport simulations in a reasonable amount of …

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 …

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 …

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 …

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 …

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 …