In this article, we propose a reduced basis method for parametrized non-symmetric eigenvalue problems arising in the loading pattern optimization of a nuclear core in neutronics. To this end, we derive a posteriori error estimates for the eigenvalue and left and right eigenvectors. The practical computation of these estimators requires the estimation of a constant called prefactor, which we can express as the spectral norm of some operator. We provide some elements of theoretical analysis which illustrate the link between the expression of the prefactor we obtain here and its well-known expression in the case of symmetric eigenvalue problems, either using the notion of numerical range of the operator, or via a perturbative analysis. Lastly,...
The alpha eigenvalue problem in multigroup neutron diffusion is studied with particular attention to...
[EN] Given a configuration of a nuclear reactor core, the neutronic distribution of the power can be...
In this work we present a methodology of solution of the multigroup multi-layer stationary neutron d...
In this article, we propose a reduced basis method for parametrized non-symmetric eigenvalue problem...
In the aim of reducing the computational cost of the resolution of parameter-dependent eigenvalue pr...
In order to analyse the steady state of a nuclear power reactor, the neutron diffusion equation in t...
6siIn nuclear engineering, the λ-modes associated with the neutron diffusion equation are applied t...
This paper deals with the extension of an existing code developed at the Department of Nuclear Engin...
International audienceThe multigroup neutron $SP_N$ equations, which are an approximation of the neu...
[EN] Mixed-dual formulations of the finite element method were successfully applied to the neutron d...
In this paper, numerical methods aiming at determining the eigenfunctions, their adjoint and the cor...
International audienceThis paper is concerned with the homogenization of an eigenvalue problem in a ...
The alpha eigenvalue problem in multigroup neutron diffusion is studied with particular attention to...
[EN] Given a configuration of a nuclear reactor core, the neutronic distribution of the power can be...
In this work we present a methodology of solution of the multigroup multi-layer stationary neutron d...
In this article, we propose a reduced basis method for parametrized non-symmetric eigenvalue problem...
In the aim of reducing the computational cost of the resolution of parameter-dependent eigenvalue pr...
In order to analyse the steady state of a nuclear power reactor, the neutron diffusion equation in t...
6siIn nuclear engineering, the λ-modes associated with the neutron diffusion equation are applied t...
This paper deals with the extension of an existing code developed at the Department of Nuclear Engin...
International audienceThe multigroup neutron $SP_N$ equations, which are an approximation of the neu...
[EN] Mixed-dual formulations of the finite element method were successfully applied to the neutron d...
In this paper, numerical methods aiming at determining the eigenfunctions, their adjoint and the cor...
International audienceThis paper is concerned with the homogenization of an eigenvalue problem in a ...
The alpha eigenvalue problem in multigroup neutron diffusion is studied with particular attention to...
[EN] Given a configuration of a nuclear reactor core, the neutronic distribution of the power can be...
In this work we present a methodology of solution of the multigroup multi-layer stationary neutron d...