Reconstruction of the Neutron Flux in a Slab Reactor

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World Journal of Nuclear Science and Technology

ISSN Print: 2161-6795
ISSN Online: 2161-6809
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"Reconstruction of the Neutron Flux in a Slab Reactor"
written by Adilson Costa da Silva, Aquilino Senra Martinez, Alessandro da Cruz Gonçalves,
published by World Journal of Nuclear Science and Technology, Vol.2 No.4, 2012

has been cited by the following article(s):

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[2]	Solução de problemas estacionários e transientes da teoria da difusão de nêutrons multigrupo em geometria cartesiana via abordagens nodais e exponenciais …
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[3]	Cálculo de criticalidade pela teoria de difusão de nêutrons: uma análise comparativa de aproximação da densidade de corrente
	2020

[4]	Solution of the multilayer multigroup neutron diffusion equation in cartesian geometry by fictitious borders power method
	2017

[5]	Solução da Equação de Difusão de Nêutrons Multigrupo Multirregião Estacionária Unidimensional em Geometria Cartesiana pelo Método da Potência via …
	2017

[6]	Ingegneria Energetica, Nucleare e del Controllo Ambientale
	Dissertation, 2016

[7]	Finite Element Method with Spectral Green's Function in Slab Geometry for Neutron Diffusion in Multiplying Media and One Energy Group
	2016

[8]	Calcoli di sezioni d'urto efficaci di riflettore in sistemi PWR di terza generazione
	2015

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[1]	Determination of Neutron Flux Viewed from the Maxwell-Boltzmann’s Statistical Distribution Using Numerical Approach Journal of Physics: Conference Series, 2021 DOI:10.1088/1742-6596/1805/1/012046

[2]	Solution of the multilayer multigroup neutron diffusion equation in cartesian geometry by fictitious borders power method Kerntechnik, 2017 DOI:10.3139/124.110682