This paper presents new algorithms for use in the eigenvalue response matrix method (ERMM) for reactor eigenvalue problems. ERMM spatially decomposes a domain into independent nodes linked via boundary conditions approximated as truncated orthogonal expansions, the coefficients of which are response functions. In its simplest form, ERMM consists of a two-level eigenproblem: an outer Picard iteration updates the k-eigenvalue via balance, while the inner λ -eigenproblem imposes neutron balance between nodes. Efficient methods are developed for solving the inner λ-eigenvalue problem within the outer Picard iteration. Based on results from several diffusion and transport benchmark models, it was found that the Krylov-Schur method applied to th...
International audienceThe simulation of the neutron transport inside a nuclear reactor leads to the ...
The solution of the eigenvalue problem for neutron transport is of utmost importance in the field o...
International audienceThis work investigates the solution of the multigroup neutron transport equati...
This paper presents new algorithms for use in the eigenvalue response matrix method (ERMM) for react...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
[EN] Given a configuration of a nuclear reactor core, the neutronic distribution of the power can be...
[EN] The spatial distribution of the neutron flux within the core of nuclear reactors is a key facto...
[EN] The dominant lambda-modes associated with a nuclear reactor configuration describe the neutron ...
Graduate School. In this work we propose using Newton’s method, specifically the inexact Newton-GMRE...
International audienceThis work investigates the solution of the multigroup neutron transport equati...
[EN] Mixed-dual formulations of the finite element method were successfully applied to the neutron d...
The alpha- and k-effective eigenproblems describe the criticality and fundamental neutron flux mode ...
Three complementary methods have been implemented in the code Denovo that accelerate neutral particl...
6siIn nuclear engineering, the λ-modes associated with the neutron diffusion equation are applied t...
Using an autoencoder for dimensionality reduction, this article presents a novel projection‐based re...
International audienceThe simulation of the neutron transport inside a nuclear reactor leads to the ...
The solution of the eigenvalue problem for neutron transport is of utmost importance in the field o...
International audienceThis work investigates the solution of the multigroup neutron transport equati...
This paper presents new algorithms for use in the eigenvalue response matrix method (ERMM) for react...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
[EN] Given a configuration of a nuclear reactor core, the neutronic distribution of the power can be...
[EN] The spatial distribution of the neutron flux within the core of nuclear reactors is a key facto...
[EN] The dominant lambda-modes associated with a nuclear reactor configuration describe the neutron ...
Graduate School. In this work we propose using Newton’s method, specifically the inexact Newton-GMRE...
International audienceThis work investigates the solution of the multigroup neutron transport equati...
[EN] Mixed-dual formulations of the finite element method were successfully applied to the neutron d...
The alpha- and k-effective eigenproblems describe the criticality and fundamental neutron flux mode ...
Three complementary methods have been implemented in the code Denovo that accelerate neutral particl...
6siIn nuclear engineering, the λ-modes associated with the neutron diffusion equation are applied t...
Using an autoencoder for dimensionality reduction, this article presents a novel projection‐based re...
International audienceThe simulation of the neutron transport inside a nuclear reactor leads to the ...
The solution of the eigenvalue problem for neutron transport is of utmost importance in the field o...
International audienceThis work investigates the solution of the multigroup neutron transport equati...