The different neutronic parameters have to be calculated with a higher accuracy in order to design the 4th generation reactor cores. As memory storage and computation time are limited, adaptive methods are a solution to solve the neutron transport equation. The neutronic flux, solution of this equation, depends on the energy, angle and space. The different variables are successively discretized. The energy with a multigroup approach, considering the different quantities to be constant on each group, the angle by a collocation method called Sn approximation. Once the energy and angle variable are discretized, a system of spatially-dependent hyperbolic equations has to be solved. Discontinuous finite elements are used to make possible the dev...
The purpose of this PhD is the implementation of an axial polynomial approximation in a three-dimens...
Adaptive grid refinement strategies have been formulated to solve the even parity Boltzmann transpor...
This PhD thesis focuses on the neutronics design of experimental configurations to improve knowledge...
Pour la conception des cœurs de réacteurs de 4ème génération, une précision accrue est requise pour ...
We consider high order discontinuous-Galerkin finite element methods for partial differential equati...
[EN] The simplified spherical harmonics approximation to the neutron transport equation defines the ...
International audienceThis paper presents a hp−refinement method for a first order scalar transport-...
Cette thèse traite des méthodes d’éléments finis Galerkin discontinus d’ordre élevé pour la résoluti...
In this article we consider the application of high-order/hp-version adaptive discontinuous Galerkin...
In this thesis we study the neutron transport (Boltzmann transport equation) which is used to model ...
The multigroup neutron $SP_N$ equations, which are an approximation of the neutron transport equatio...
Modern nuclear reactors utilize core calculations that implement a thermo-hydraulic feedback requiri...
Nuclear reactor design requires the calculation of integral core parameters and power and radiation ...
In this thesis, we have first developed a time dependent 3D neutron transport solver on unstructured...
Multiphysics coupling is becoming of large interest in the nuclear engineering and computational sci...
The purpose of this PhD is the implementation of an axial polynomial approximation in a three-dimens...
Adaptive grid refinement strategies have been formulated to solve the even parity Boltzmann transpor...
This PhD thesis focuses on the neutronics design of experimental configurations to improve knowledge...
Pour la conception des cœurs de réacteurs de 4ème génération, une précision accrue est requise pour ...
We consider high order discontinuous-Galerkin finite element methods for partial differential equati...
[EN] The simplified spherical harmonics approximation to the neutron transport equation defines the ...
International audienceThis paper presents a hp−refinement method for a first order scalar transport-...
Cette thèse traite des méthodes d’éléments finis Galerkin discontinus d’ordre élevé pour la résoluti...
In this article we consider the application of high-order/hp-version adaptive discontinuous Galerkin...
In this thesis we study the neutron transport (Boltzmann transport equation) which is used to model ...
The multigroup neutron $SP_N$ equations, which are an approximation of the neutron transport equatio...
Modern nuclear reactors utilize core calculations that implement a thermo-hydraulic feedback requiri...
Nuclear reactor design requires the calculation of integral core parameters and power and radiation ...
In this thesis, we have first developed a time dependent 3D neutron transport solver on unstructured...
Multiphysics coupling is becoming of large interest in the nuclear engineering and computational sci...
The purpose of this PhD is the implementation of an axial polynomial approximation in a three-dimens...
Adaptive grid refinement strategies have been formulated to solve the even parity Boltzmann transpor...
This PhD thesis focuses on the neutronics design of experimental configurations to improve knowledge...