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Development of neutron shielding for an inertial electrostatic confinement nuclear fusion device

LEE, SEUNG M.; YORIYAZ, HELIO; CABRAL, EDUARDO L.L.; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE (Associa????o Brasileira de Energia Nuclear, 2020)

Neutron Guide Building instruments of the Brazilian Multipurpose Reactor (RMB) project

SOUZA, A.P.S.; OLIVEIRA, L.P. de; YOKAICHIYA, F.; GENEZINI, F.A.; FRANCO, M.K.K.D. (2020)

Teoria de transporte de neutrons em meios adjacentes no modelo de dois grupos e espalhamento isotropico

MAIORINO, JOSE R. (1976)

Estudo preliminar dos parametros de difusao da agua para neutrons termicos pelo metodo da fonte pulsada

CARVALHO, M.; PAIANO SOBRINHO, S. (1965)

Two-group neutron-transport theory with linearly anisotropic scattering: half-range orthogonality and critical slab problem

ISHIGURO, Y. (1973)

Neutron flux calculation in a BNCT research facility implemented in IEA-R1 reactor

COELHO, P.R.P.; HERNANDES, A.C.; SIQUEIRA, P.T.D.; RESEARCH AND DEVELOPMENT IN NEUTRON CAPTURE THERAPY (Bologna: Monduzzi Editore, 2002, 2014)

Monte Carlo simulations of the S-shaped neutron guide

OLIVEIRA, L.P. de; SOUZA, A.P.S.; YOKAICHIYA, F.; GENEZINI, F.A.; FRANCO, M.K.K.D. (2020)

Half-range orthogonality theorem for thermal neutron transport

ISHIGURO, Y. (1975)

Avalia????o de dados nucleares para dosimetria de n??utronsEvaluation of nuclear data for neutron dosimetry

TARDELLI, TIAGO C. (2013)

Future perspectives for neutron beam utilization in Brasil

PERROTTA, J.A.; SOARES, A.J.; GENEZINI, F.A.; SOUZA, F.A.; FRANCO, M.K.K.D.; GRANADO, E. (2014)

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