International audienceIn the framework of nuclear core calculations, the development of efficient tools to run neutron kinetic computations is a field of current active research. While such calculations are crucial for security assessment and the study of new reactor concepts, they present several mathematical and computational issues that still need to be overcome. The exact model (kinetic transport equation) is indeed far too expensive to be simulated for these purposes and different simplifications (multi group diffusion approximation) have led to more tractable numerical simulations. Nevertheless, on real geometries and despite the use of domain decomposition enabling accelerations of the simulations thanks to parallel architectures, th...
In this work we solve the space kinetic diffusion equation in a one-dimensional geometry considering...
In this thesis, we have first developed a time dependent 3D neutron transport solver on unstructured...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
International audienceIn the framework of nuclear core calculations, the development of efficient to...
International audienceAbstract In this paper we present a time-parallel algorithm for the 3D neutron...
International audienceThe present paper deals with the resolution of the time-dependent neutron tran...
The accurate knowledge of the time-dependent spatial flux distribution in nuclear reactor is require...
In the search of new approaches for the efficient exploitation of large scale compu- tational platfo...
This thesis presents algorithms allowing parallelization in the time-direction of the simulation of ...
This thesis presents algorithms allowing parallelization in the time direction in the simulation of ...
Dans cette thèse nous avons tout d'abord développé un solveur neutronique de cinétique transport 3D ...
We present the newly developed time-dependent 3D multigroup discrete ordinates neutron transport sol...
In this paper, we propose a variant of the parareal algorithm for time-dependent problems involving ...
High-fidelity nuclear reactor core simulations require a precise knowledge of the neutron flux insid...
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1972. Ph.D.Vita.Include...
In this work we solve the space kinetic diffusion equation in a one-dimensional geometry considering...
In this thesis, we have first developed a time dependent 3D neutron transport solver on unstructured...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
International audienceIn the framework of nuclear core calculations, the development of efficient to...
International audienceAbstract In this paper we present a time-parallel algorithm for the 3D neutron...
International audienceThe present paper deals with the resolution of the time-dependent neutron tran...
The accurate knowledge of the time-dependent spatial flux distribution in nuclear reactor is require...
In the search of new approaches for the efficient exploitation of large scale compu- tational platfo...
This thesis presents algorithms allowing parallelization in the time-direction of the simulation of ...
This thesis presents algorithms allowing parallelization in the time direction in the simulation of ...
Dans cette thèse nous avons tout d'abord développé un solveur neutronique de cinétique transport 3D ...
We present the newly developed time-dependent 3D multigroup discrete ordinates neutron transport sol...
In this paper, we propose a variant of the parareal algorithm for time-dependent problems involving ...
High-fidelity nuclear reactor core simulations require a precise knowledge of the neutron flux insid...
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1972. Ph.D.Vita.Include...
In this work we solve the space kinetic diffusion equation in a one-dimensional geometry considering...
In this thesis, we have first developed a time dependent 3D neutron transport solver on unstructured...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...