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Listar por palabra clave "Neutron diffusion equation"

Mostrando ítems 1-11 de 11

A Krylov-Schur solution of the eigenvalue problem for the neutron diffusion equation discretized with the Raviart-Thomas method

Bernal-Garcia, Alvaro; Hébert, Alain; Roman, Jose E.; Miró Herrero, Rafael; Verdú Martín, Gumersindo Jesús (Taylor & Francis, 2017)

[EN] Mixed-dual formulations of the finite element method were successfully applied to the neutron diffusion equation, such as the Raviart¿Thomas method in Cartesian geometry and the Raviart¿Thomas¿Schneider in hexagonal ...
Block hybrid multilevel method to compute the dominant lambda-modes of the neutron diffusion equation

Carreño, A.; Vidal-Ferràndiz, Antoni; Ginestar Peiro, Damián; Verdú Martín, Gumersindo Jesús (Elsevier, 2018)

[EN] The dominant lambda-modes associated with a nuclear reactor configuration describe the neutron steady-state distribution and its criticality. Furthermore, they are useful to develop modal methods to study reactor ...
Block Preconditioning Matrices for the Newton Method to Compute the Dominant lambda-Modes Associated with the Neutron Diffusion Equation

Carreño, Amanda; Bergamaschi, Luca; Martinez, Angeles; Vidal-Ferràndiz, Antoni; Ginestar Peiro, Damián; Verdú Martín, Gumersindo Jesús (MDPI AG, 2019-03)

[EN] In nuclear engineering, the lambda-modes associated with the neutron diffusion equation are applied to study the criticality of reactors and to develop modal methods for the transient analysis. The differential ...
Calculation of multiple eigenvalues of the neutron diffusion equation discretized with a parallelized finite volume method

Bernal-Garcia, Alvaro; Roman, Jose E.; Miró Herrero, Rafael; Verdú Martín, Gumersindo Jesús (Elsevier, 2018)

[EN] The spatial distribution of the neutron flux within the core of nuclear reactors is a key factor in nuclear safety. The easiest and fastest way to determine it is by solving the eigenvalue problem of the neutron ...
Contributions to solve the Multi-group Neutron Transport equation with different Angular Approaches

Morato Rafet, Sergio (Universitat Politècnica de València, 2021-01-17)

[ES] La forma más exacta de conocer el desplazamiento de los neutrones a través de un medio material se consigue resolviendo la Ecuación del Transporte Neutrónico. Tres diferentes aproximaciones de esta ecuación se han ...
Development of a Finite Volume Inter-cell Polynomial Expansion Method for the Neutron Diffusion Equation

Bernal García, Álvaro; Román Moltó, José Enrique; Miró Herrero, Rafael; Ginestar Peiro, Damián; Verdú Martín, Gumersindo Jesús (Taylor & Francis, 2016)

Heterogeneous nuclear reactors require numerical methods to solve the neutron diffusion equation (NDE) to obtain the neutron flux distribution inside them, by discretizing the heterogeneous geometry in a set of homogeneous ...
Moving meshes to solve the time-dependent neutron diffusion equation in hexagonal geometry

Vidal-Ferràndiz, Antoni; Fayez Moustafa Moawad, Ragab; Ginestar Peiro, Damián; Verdú Martín, Gumersindo Jesús (Elsevier, 2016-01)

To simulate the behaviour of a nuclear power reactor it is necessary to be able to integrate the time-dependent neutron diffusion equation inside the reactor core. Here the spatial discretization of this equation is done ...
Multigroup neutron diffusion equation with the finite volume method in reactors using MOX fuels

Bernal-Garcia, Alvaro; Roman, Jose E.; Miró Herrero, Rafael; Verdú Martín, Gumersindo Jesús (Taylor & Francis, 2017)

[EN] The use of mixed oxide (MOX) fuel to partially fill the cores of commercial light water reactors (LWRs) gives rise to a reduction of the radioactive waste and production of more energy. However, the use of MOX fuels ...
Preconditioning the solution of the time- dependent neutron diffusion equation by recycling Krylov subspaces

González Pintor, Sebastián; Ginestar Peiro, Damián; Verdú Martín, Gumersindo Jesús (Taylor & Francis, 2014-01-02)

[EN] Spectral preconditioners are based on the fact that the convergence rate of Krylov subspace methods is improved if the eigenvalues of smallest magnitude of the system matrix are `removed'. In this paper, two ...
Spatial modes for the neutron diffusion equation and their computation

Carreño, A.; Vidal-Ferràndiz, Antoni; Ginestar Peiro, Damián; Verdú Martín, Gumersindo Jesús (Elsevier, 2017)

[EN] Different spatial modes can be defined for the neutron diffusion equation such as the k; a and c-modes. These modes have been successfully used for the analysis of nuclear reactor characteristics. In this work, these ...
Use of discontinuity factors in high-order finite element methods

Vidal-Ferràndiz, Antoni; González Pintor, Sebastián; Ginestar Peiro, Damián; Verdú Martín, Gumersindo Jesús; Asadzadeh, M.; Demazière, Christophe (Elsevier Masson, 2016-01)

The discontinuity factors are a technique widely used in nodal methods to minimize the error due to spatial homogenization of cross sections for a coarse mesh core calculation. In the present work, the introduction of ...