Galerkin and Generalized Least Squares finite element: A comparative study for multi-group diffusion solvers

SA Hosseini, F Saadatian-Derakhshandeh - Progress in Nuclear Energy, 2015 - Elsevier
In this paper, the solution of multi-group neutron/adjoint equation using Finite Element
Method (FEM) for hexagonal and rectangular reactor cores is reported. The spatial …

Solution of the Lambda modes problem of a nuclear power reactor using an h–p finite element method

A Vidal-Ferrandiz, R Fayez, D Ginestar… - Annals of Nuclear Energy, 2014 - Elsevier
Lambda modes of a nuclear power reactor have interest in reactor physics since they have
been used to develop modal methods and to study BWR reactor instabilities. An h–p …

[HTML][HTML] Moving meshes to solve the time-dependent neutron diffusion equation in hexagonal geometry

A Vidal-Ferràndiz, R Fayez, D Ginestar… - Journal of computational …, 2016 - Elsevier
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 …

[HTML][HTML] Edge-wise perturbations to model vibrating fuel assemblies in the frequency-domain using FEMFFUSION: Development and verification

A Vidal-Ferràndiz, A Carreño, D Ginestar… - Annals of Nuclear …, 2022 - Elsevier
The mechanical vibrations of fuel assemblies have shown to give high levels of neutron
noise, triggering in some circumstances the necessity to operate nuclear reactors at a …

Neutron noise simulation by GFEM and unstructured triangle elements

SA Hosseini, N Vosoughi - Nuclear engineering and design, 2012 - Elsevier
In the present study, the neutron noise, ie the stationary fluctuation of the neutron flux around
its mean value, is calculated in 2-group forward and adjoint diffusion theory for both …

[HTML][HTML] Development of Galerkin finite element method three-dimensional computational code for the multigroup neutron diffusion equation with unstructured …

SA Hosseini - Nuclear Engineering and Technology, 2016 - Elsevier
In the present paper, development of the three-dimensional (3D) computational code based
on Galerkin finite element method (GFEM) for solving the multigroup forward/adjoint …

[HTML][HTML] Application of Backward Differential Formula and Anderson's method for multigroup diffusion transient equation

A Cherezov, A Vasiliev, H Ferroukhi - Annals of Nuclear Energy, 2025 - Elsevier
This paper focuses on the application of the Backward Differential Formula (BDF) and
Anderson's method for neutron diffusion transient simulations. The B-spline finite element …

WWER core pattern enhancement using adaptive improved harmony search

T Nazari, M Aghaie, A Zolfaghari, A Minuchehr… - … engineering and design, 2013 - Elsevier
The efficient operation and fuel management of PWRs are of utmost importance. Core
performance analysis constitutes an essential phase in core fuel management optimization …

Development of two-dimensional, multigroup neutron diffusion computer code based on GFEM with unstructured triangle elements

SA Hosseini, N Vosoughi - Annals of Nuclear Energy, 2013 - Elsevier
Various methods for solving the forward/adjoint equation in hexagonal and rectangular
geometries are known in the literatures. In this paper, the solution of multigroup …

[HTML][HTML] Time integration of the neutron diffusion equation on hexagonal geometries

S González-Pintor, D Ginestar, G Verdú - Mathematical and Computer …, 2010 - Elsevier
To study the behavior of nuclear reactors like the Russian VVER reactors it is necessary to
solve the time dependent neutron diffusion equation using a hexagonal mesh. Two methods …