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Published in:
Neutron Physics Background Read chapter Read first chapter

2019 | OriginalPaper | Chapter

5. Numerical Methods in Modeling Neutron Diffusion

Author : Bahman Zohuri

Published in: Neutronic Analysis For Nuclear Reactor Systems

Publisher: Springer International Publishing

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Abstract

The constructive techniques of functional analysis, using a computer code, allow us to build up directly, in their original domain of definition, solutions to linear transport equation. FEMP code is a computer code written in FORTRAN 77, to approximate the Boltzmann transport equation in one-dimensional form using a spherical harmonic for the angular variable and a linear finite element for the spatial variable.

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previous chapter Energy Effects in Modeling Neutron Diffusion: Two-Group Models
next chapter Slowing Down Theory
Literature
1.
McDaniel P. Finite element multi-group PN 1-dimensional computer code, User’s manual. Albuquerque: University of New Mexico; 2007
Metadata
Title
Numerical Methods in Modeling Neutron Diffusion
Author
Bahman Zohuri
Copyright Year
2019
Book
Neutronic Analysis For Nuclear Reactor Systems

Print ISBN: 978-3-030-04905-8

Electronic ISBN: 978-3-030-04906-5

Copyright Year: 2019

DOI
https://doi.org/10.1007/978-3-030-04906-5_5