Approximation of The Neutron Diffusion Equation on Hexagonal Geometries Using a h-p finite element method

Approximation of The Neutron Diffusion Equation on Hexagonal Geometries Using a h-p finite element method

[EN] The neutron diffusion equation is an approximation of the neutron transport equation that describes the neutron population in a nuclear reactor core. In particular, we will consider here VVER-type reactors which use the neutron diffusion equation discretized on hexagonal meshes. Most of the sim...

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Bibliographic Details
Main Author: Fayez Moustafa Moawad, Ragab
Other Authors: Ginestar Peiro, Damián
Format: Doctoral Thesis
Language:English
Published: Universitat Politècnica de València 2016
Subjects:
Lambda Modes
H-p-adaptability
Eigenvalue problems
Rod-cusping problem
Moving mesh scheme
Neitron diffusion equation
Finite Element Method
Neutron SPN equations
Spherical harmonics
MATEMATICA APLICADA
INGENIERIA NUCLEAR
Online Access:http://hdl.handle.net/10251/65353

Internet

http://hdl.handle.net/10251/65353

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