In this paper, numerical methods aiming at determining the eigenfunctions, their adjoint and the corresponding eigenvalues of the two-group neutron diffusion equations representing any heterogeneous system are investigated. First, the classical power iteration method is modified so that the calculation of modes higher than the fundamental mode is possible. Thereafter, the explicitly-restarted Arnoldi method, belonging to the class of Krylov subspace methods, is touched upon. Although the modified power iteration method is a computationally-expensive algorithm, its main advantage is its robustness, i.e. the method always converges to the desired eigenfunctions without any need from the user to set up any parameter in the algorithm. On the ot...
Neutron noise analysis techniques are studied and developed, with primary useof determining the stab...
In control-oriented simulators, the neutronics is usually modeled by implementing the point-wise kin...
The alpha eigenvalue problem in multigroup neutron diffusion is studied with particular attention to...
In this paper, numerical methods aiming at determining the eigenfunctions, their adjoint and the cor...
This paper deals with the extension of an existing code developed at the Department of Nuclear Engin...
[EN] In-phase and out-of-phase oscillations have been observed in BWR reactors. To improve the safet...
Abstract: Algorithms are obtained to compute spatial kinetics of nuclear reactor in diffus...
In this work we present a methodology of solution of the multigroup multi-layer stationary neutron d...
[EN] Mixed-dual formulations of the finite element method were successfully applied to the neutron d...
The article discusses the neutron flux stability in the core of a high-power sodium-cooled fast reac...
The paper presents the development of a strategy for the fine-mesh full-core computation of neutron ...
The distribution of the power inside a reactor core can be described by the time dependent multigrou...
In this thesis we present a method to generatethe natural spacial modes of an atomic reactor model f...
A simple nonlinear Reduced Order Model to study global, regional and local instabilities in Boiling ...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
Neutron noise analysis techniques are studied and developed, with primary useof determining the stab...
In control-oriented simulators, the neutronics is usually modeled by implementing the point-wise kin...
The alpha eigenvalue problem in multigroup neutron diffusion is studied with particular attention to...
In this paper, numerical methods aiming at determining the eigenfunctions, their adjoint and the cor...
This paper deals with the extension of an existing code developed at the Department of Nuclear Engin...
[EN] In-phase and out-of-phase oscillations have been observed in BWR reactors. To improve the safet...
Abstract: Algorithms are obtained to compute spatial kinetics of nuclear reactor in diffus...
In this work we present a methodology of solution of the multigroup multi-layer stationary neutron d...
[EN] Mixed-dual formulations of the finite element method were successfully applied to the neutron d...
The article discusses the neutron flux stability in the core of a high-power sodium-cooled fast reac...
The paper presents the development of a strategy for the fine-mesh full-core computation of neutron ...
The distribution of the power inside a reactor core can be described by the time dependent multigrou...
In this thesis we present a method to generatethe natural spacial modes of an atomic reactor model f...
A simple nonlinear Reduced Order Model to study global, regional and local instabilities in Boiling ...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
Neutron noise analysis techniques are studied and developed, with primary useof determining the stab...
In control-oriented simulators, the neutronics is usually modeled by implementing the point-wise kin...
The alpha eigenvalue problem in multigroup neutron diffusion is studied with particular attention to...