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Numerical Methods in Modeling Neutron Diffusion

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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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Reference

  1. P. McDaniel, Finite Element Multi-Group PN 1-Dimensional Computer Code, User’s Manual, University of New Mexico, Albuquerque, New Mexico (March 8, 2007)

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This chapter has no problem developed for it except you need to obtain FEMB computer code. Please contact the author of the book at bahmanz@aol.com

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Zohuri, B. (2017). Numerical Methods in Modeling Neutron Diffusion. In: Neutronic Analysis For Nuclear Reactor Systems. Springer, Cham. https://doi.org/10.1007/978-3-319-42964-9_5

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  • DOI: https://doi.org/10.1007/978-3-319-42964-9_5

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  • Publisher Name: Springer, Cham

  • Print ISBN: 978-3-319-42962-5

  • Online ISBN: 978-3-319-42964-9

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