On multi-group neutron transport in planar one dimensional geometry: A solution for a localized pulsed source

Author:

Fernandes J.C.L.,Bodmann B.E.J.,Vilhena M.T.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference19 articles.

1. Space asymptotic method for the study of neutron propagation;Dulla;Ann. Nucl. Energy,2006

2. Fernandes, J.C.L., 2015. Multi-group Neutron transport Equation Solution in Nuclear Reactors with Pulsed Sources (PhD Thesis), UFRGS.

3. Fernandes, J.C.L., Dulla, S., Ravetto, P., Vilhena, M.T., 2015. Multi-group Neutron Propagation in Transport Theory by Space Asymptotic Methods, Integral Methods in Science and Engineering, pp 223–234, Birkhauser.

4. Multigroup neutron transport;Belleni;J. Math. Phys.,1972

5. Analytical Solutions to discrete ordinate time-dependent transport problems;Dulla;Trans. Am. Nucl. Soc.,2004

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