In this paper we present a time-parallel algorithm for the 3D neutrons calculation of a transient model in a nuclear reactor core. The neutrons calculation consists in numerically solving the time dependent diffusion approximation equation, which is a simplified transport equation. The numerical resolution is done with finite elements method based on a tetrahedral meshing of the computational domain, representing the reactor core, and time discretization is achieved using a θ-scheme. The transient model presents moving control rods during the time of the reaction. Therefore, cross-sections (piecewise constants) are taken into account by interpolations with respect to the velocity of the control rods. The parallelism across the time is achie...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
To simulate the behaviour of a nuclear power reactor it is necessary to be able to integrate the tim...
A neutronic module for the solution of two-dimensional steady-state multigroup diffusion problems in...
International audienceAbstract In this paper we present a time-parallel algorithm for the 3D neutron...
The accurate knowledge of the time-dependent spatial flux distribution in nuclear reactor is require...
International audienceIn the framework of nuclear core calculations, the development of efficient to...
We present the newly developed time-dependent 3D multigroup discrete ordinates neutron transport sol...
In the search of new approaches for the efficient exploitation of large scale compu- tational platfo...
Three-dimensional, full core modeling with pin-resolved detail has become the state of the art in co...
New solution methods suitable for efficient parallel computation of reactor spatial kinetics problem...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
In this thesis, we have first developed a time dependent 3D neutron transport solver on unstructured...
Dans cette thèse nous avons tout d'abord développé un solveur neutronique de cinétique transport 3D ...
In this work, two approaches, based on the certified Reduced Basis method, have been developed for s...
Recently [5, 6, 7] a discretization (in time) scheme for the transient even-parity neutron transport...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
To simulate the behaviour of a nuclear power reactor it is necessary to be able to integrate the tim...
A neutronic module for the solution of two-dimensional steady-state multigroup diffusion problems in...
International audienceAbstract In this paper we present a time-parallel algorithm for the 3D neutron...
The accurate knowledge of the time-dependent spatial flux distribution in nuclear reactor is require...
International audienceIn the framework of nuclear core calculations, the development of efficient to...
We present the newly developed time-dependent 3D multigroup discrete ordinates neutron transport sol...
In the search of new approaches for the efficient exploitation of large scale compu- tational platfo...
Three-dimensional, full core modeling with pin-resolved detail has become the state of the art in co...
New solution methods suitable for efficient parallel computation of reactor spatial kinetics problem...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
In this thesis, we have first developed a time dependent 3D neutron transport solver on unstructured...
Dans cette thèse nous avons tout d'abord développé un solveur neutronique de cinétique transport 3D ...
In this work, two approaches, based on the certified Reduced Basis method, have been developed for s...
Recently [5, 6, 7] a discretization (in time) scheme for the transient even-parity neutron transport...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
To simulate the behaviour of a nuclear power reactor it is necessary to be able to integrate the tim...
A neutronic module for the solution of two-dimensional steady-state multigroup diffusion problems in...