Titlebook: Neutronic Analysis For Nuclear Reactor Systems; Bahman Zohuri Book 20171st edition Springer International Publishing Switzerland 2017 Hete

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Spatial Effects in Modeling Neutron Diffusion: One-Group Models,lear design calculation is the effective multiplication factor (.) and neutron flux distribution. We also so far have noticed that the excess reactivity, control rod worth, reactivity coefficient, power distribution, etc., are undoubtedly inseparable from the nuclear design calculation. Some quantit

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Numerical Methods in Modeling Neutron Diffusion,tions 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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