We develop a fully analytical study of the spectrum of the neutron diffusion operator both for spatially homogeneous and reflected reactors in a multi-group energy model. We illustrate and discuss the results of the analysis of the time spectrum of the diffusion operator, to highlight some general properties of the neutronic evolution in a multiplying system. Various new results are presented, particularly regarding the possible existence of complex time eigenvalues, the appearance of a continuum part of the spectrum and the orthogonality properties of the eigenfunctions in the case of an infinite reflect
Owing to their inherent complexity, stochastic neutron transport problems are often examined by eith...
Abstract: We present a new approach to calculating time eigenvalues of the neutron transport operato...
A simple model of time-independent neutron transport on a line as a stochastic process, using the me...
The present work addresses the problem of the determination of the eigenvalue spectrum of the multig...
This paper is concerned with the homogenization of an eigenvalue problem in a periodic heterogeneous...
The alpha eigenvalue problem in multigroup neutron diffusion is studied with particular attention to...
This paper is devoted to the physics of a homogeneous fluid-fuel system with perfect remixing. The o...
The study of the steady-state solutions of neutron transport equation requires the introduction of a...
M&C 2017 - International Conference on Mathematics & Computational Methods Applied to Nuclear Scienc...
The theory of the pulsed neutron experiment and the 2 zone exponential experiment is developed in th...
In this paper we study the homogenization of an eigenvalue problem for a cooperative system of weakl...
In this thesis we present a method to generatethe natural spacial modes of an atomic reactor model f...
Abstract: Algorithms are obtained to compute spatial kinetics of nuclear reactor in diffus...
[[abstract]]A rigorous description of nuclear reactor kinetics usually invokes neutron transport the...
In this paper, numerical methods aiming at determining the eigenfunctions, their adjoint and the cor...
Owing to their inherent complexity, stochastic neutron transport problems are often examined by eith...
Abstract: We present a new approach to calculating time eigenvalues of the neutron transport operato...
A simple model of time-independent neutron transport on a line as a stochastic process, using the me...
The present work addresses the problem of the determination of the eigenvalue spectrum of the multig...
This paper is concerned with the homogenization of an eigenvalue problem in a periodic heterogeneous...
The alpha eigenvalue problem in multigroup neutron diffusion is studied with particular attention to...
This paper is devoted to the physics of a homogeneous fluid-fuel system with perfect remixing. The o...
The study of the steady-state solutions of neutron transport equation requires the introduction of a...
M&C 2017 - International Conference on Mathematics & Computational Methods Applied to Nuclear Scienc...
The theory of the pulsed neutron experiment and the 2 zone exponential experiment is developed in th...
In this paper we study the homogenization of an eigenvalue problem for a cooperative system of weakl...
In this thesis we present a method to generatethe natural spacial modes of an atomic reactor model f...
Abstract: Algorithms are obtained to compute spatial kinetics of nuclear reactor in diffus...
[[abstract]]A rigorous description of nuclear reactor kinetics usually invokes neutron transport the...
In this paper, numerical methods aiming at determining the eigenfunctions, their adjoint and the cor...
Owing to their inherent complexity, stochastic neutron transport problems are often examined by eith...
Abstract: We present a new approach to calculating time eigenvalues of the neutron transport operato...
A simple model of time-independent neutron transport on a line as a stochastic process, using the me...