International audienceThis paper presents an efficient parallel method for the deterministic solution of the 3D stationary Boltzmann transport equation applied to diffusive problems such as nuclear core criticality computations. Based on standard MultiGroup-Sn-DD discretization schemes, our approach combines a highly efficient nested parallelization strategy [1] with the PDSA parallel acceleration technique [2] applied for the first time to 3D transport problems. These two key ingredients enable us to solve extremely large neutronic problems involving up to 10 12 degrees of freedom in less than an hour using 64 super-computer nodes
International audienceA reactivity computation consists of computing the highest eigenvalue of a gen...
<p>Today’s “grand challenge” neutron transport problems require 3-D meshes with billions of cells,<b...
The problem of energetic nucleon transport through extended bulk matter is considered in the context...
International audienceHigh-fidelity nuclear power plant core simulations require solving the Boltzma...
In this paper we solve the Boltzmann transport equation using AI libraries. The reason why this is a...
The linear Boltzmann transport equation (BTE) is an integro-differential equation arising in determi...
High-fidelity nuclear reactor core simulations require a precise knowledge of the neutron flux insid...
We present here MINARET a deterministic transport solver for nuclear core calculations to solve the ...
This paper outlines the implementation and performance of a parallelisation approach involving parti...
The Boltzmann transport equation is solved by means of a parallel explicit algorithm known as parall...
Abstract: The Boltzmann transport equation is solved by means of a parallel explicit algorithm known...
The main goal of this work is to examine efficient methods for solving neutron transport and diffusi...
The multigrid method has been shown to be the most effective general method for solving the multi-di...
The focus of the research was on developing parallel computing algorithm for solving eigen-values of...
The work performed in this project consisted of the derivation, implementation, and testing of a new...
International audienceA reactivity computation consists of computing the highest eigenvalue of a gen...
<p>Today’s “grand challenge” neutron transport problems require 3-D meshes with billions of cells,<b...
The problem of energetic nucleon transport through extended bulk matter is considered in the context...
International audienceHigh-fidelity nuclear power plant core simulations require solving the Boltzma...
In this paper we solve the Boltzmann transport equation using AI libraries. The reason why this is a...
The linear Boltzmann transport equation (BTE) is an integro-differential equation arising in determi...
High-fidelity nuclear reactor core simulations require a precise knowledge of the neutron flux insid...
We present here MINARET a deterministic transport solver for nuclear core calculations to solve the ...
This paper outlines the implementation and performance of a parallelisation approach involving parti...
The Boltzmann transport equation is solved by means of a parallel explicit algorithm known as parall...
Abstract: The Boltzmann transport equation is solved by means of a parallel explicit algorithm known...
The main goal of this work is to examine efficient methods for solving neutron transport and diffusi...
The multigrid method has been shown to be the most effective general method for solving the multi-di...
The focus of the research was on developing parallel computing algorithm for solving eigen-values of...
The work performed in this project consisted of the derivation, implementation, and testing of a new...
International audienceA reactivity computation consists of computing the highest eigenvalue of a gen...
<p>Today’s “grand challenge” neutron transport problems require 3-D meshes with billions of cells,<b...
The problem of energetic nucleon transport through extended bulk matter is considered in the context...