International audienceStudying numerically the steady state of a nuclear core reactor is expensive, in terms of memory storage and computational time. In order to address both requirements, one can use a domain decomposition method, implemented on a parallel computer. We present here such a method applied to the neutron SPN equations, which are an approximation of the transport neutron equation. This method is based on the Schwarz iterative algorithm with optimized Robin interface conditions to handle communications. From a computational point of view, this method is rather easy to implement. We give some numerical results in highly heterogeneous 3D configurations. Computations are carried out with the MINOS solver, which is a multigroup SP...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
Cell by cell homogenized transport calculations of an entire nuclear reactor core are currently too ...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
International audienceStudying numerically the steady state of a nuclear core reactor is expensive, ...
International audienceIn this article we present a domain decomposition method for the mixed SPN equ...
Les calculs de réactivité constituent une brique fondamentale dans la simulation des coeurs des réac...
Les schémas de calcul déterministes permettent une modélisation à moindre coût du comportement de la...
The neutronic simulation of a nuclear reactor core is performed using the neutron transport equation...
In this thesis, we investigate the resolution of the SPN neutron transport equations in pressurized ...
International audienceThe simulation of the neutron transport inside a nuclear reactor leads to the ...
International audienceThis paper presents two parallel Simplified PN (SPN) solver implementations fo...
Domain decomposition is a mature methodology that has been used to accelerate the convergence of par...
New solution methods suitable for efficient parallel computation of reactor spatial kinetics problem...
International audienceThe simulation of the neutron transport inside a nuclear reactor leads to the ...
International audienceThe multigroup neutron $SP_N$ equations, which are an approximation of the neu...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
Cell by cell homogenized transport calculations of an entire nuclear reactor core are currently too ...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
International audienceStudying numerically the steady state of a nuclear core reactor is expensive, ...
International audienceIn this article we present a domain decomposition method for the mixed SPN equ...
Les calculs de réactivité constituent une brique fondamentale dans la simulation des coeurs des réac...
Les schémas de calcul déterministes permettent une modélisation à moindre coût du comportement de la...
The neutronic simulation of a nuclear reactor core is performed using the neutron transport equation...
In this thesis, we investigate the resolution of the SPN neutron transport equations in pressurized ...
International audienceThe simulation of the neutron transport inside a nuclear reactor leads to the ...
International audienceThis paper presents two parallel Simplified PN (SPN) solver implementations fo...
Domain decomposition is a mature methodology that has been used to accelerate the convergence of par...
New solution methods suitable for efficient parallel computation of reactor spatial kinetics problem...
International audienceThe simulation of the neutron transport inside a nuclear reactor leads to the ...
International audienceThe multigroup neutron $SP_N$ equations, which are an approximation of the neu...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
Cell by cell homogenized transport calculations of an entire nuclear reactor core are currently too ...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...