The past few years have been marked by a noticeable increase in the interest in 3D whole-core heterogeneous deterministic neutron transport solvers for reference calculations. Due to the extremely large problem sizes tackled by such solvers, they need to use adapted numerical methods and need to be efficiently implemented to take advantage of the full computing power of modern systems. As for numerical methods, one possible approach consists in iterating over resolutions of 2D and 1D MOC problems by taking advantage of prismatic geometries. The MICADO solver, developed at EDF R&D, is a parallel implementation of such a method in distributed and shared memory systems. However it is currently unable to use SIMD vectorization to leverage the f...
The topic of our research is the application of the Method of Long Characteristics (MOC) to solve th...
In order to make conventional implicit algorithm to be applicable in large scale parallel computers ...
International audienceHigh-fidelity nuclear power plant core simulations require solving the Boltzma...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
A new approach based on the method of characteristics (MOC) is proposed to solve the neutron transpo...
The main goal of this work is to examine efficient methods for solving neutron transport and diffusi...
Scalable parallel algorithm for particle transport is one of the main application fields in high-per...
The VARIANT code solves the multigroup steady-state neutron diffusion and transport equation in thre...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
We present performance results obtained on a 128-node Cray Research T3D computer by a neutron transp...
The focus of the research was on developing parallel computing algorithm for solving eigen-values of...
The spatial heterogeneity of the next generation Gen-IV nuclear reactor core designs brings challeng...
La méthode des caractéristiques (méthode MOC) est une méthode efficace et flexible de résolution de ...
AbstractThe Monte Carlo method is a common and accurate way to model neutron transport with minimal ...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
The topic of our research is the application of the Method of Long Characteristics (MOC) to solve th...
In order to make conventional implicit algorithm to be applicable in large scale parallel computers ...
International audienceHigh-fidelity nuclear power plant core simulations require solving the Boltzma...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
A new approach based on the method of characteristics (MOC) is proposed to solve the neutron transpo...
The main goal of this work is to examine efficient methods for solving neutron transport and diffusi...
Scalable parallel algorithm for particle transport is one of the main application fields in high-per...
The VARIANT code solves the multigroup steady-state neutron diffusion and transport equation in thre...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
We present performance results obtained on a 128-node Cray Research T3D computer by a neutron transp...
The focus of the research was on developing parallel computing algorithm for solving eigen-values of...
The spatial heterogeneity of the next generation Gen-IV nuclear reactor core designs brings challeng...
La méthode des caractéristiques (méthode MOC) est une méthode efficace et flexible de résolution de ...
AbstractThe Monte Carlo method is a common and accurate way to model neutron transport with minimal ...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
The topic of our research is the application of the Method of Long Characteristics (MOC) to solve th...
In order to make conventional implicit algorithm to be applicable in large scale parallel computers ...
International audienceHigh-fidelity nuclear power plant core simulations require solving the Boltzma...