On a Parametric Representation of the Angular Neutron Flux in the Energy Range from 1 eV to 10 MeV

Author:

Chaves Barcellos Luiz F. F.,Bodmann Bardo E. J.,Vilhena Marco T.

Publisher

Springer International Publishing

Reference21 articles.

1. Barcellos, L.F., Bodmann, B.E.J., Bogado Leite, S., Vilhena, M.T.: On a continuous energy Monte Carlo simulator for neutron transport: Optimisation with fission, intermediate and thermal distributions. In: Constanda, C., Dalla Riva, M., Lamberti, P.D., Musolino, P. (eds.) Integral Methods in Science and Engineering, vol. 2. Springer, Berlin (2017)

2. Bindra, H., Patil, D.V.: Radiative or neutron transport modeling using a lattice Boltzmann equation framework. Phys. Rev. E 86, 016706 (2012)

3. De Camargo, D.Q., Bodmann, B.E.J., Vilhena, M.T., Bogado Leite, S.Q., Alvim, A.C.M.: A stochastic model for neutrons simulation considering the spectrum and nuclear properties with continuous dependence of energy. Prog. Nucl. Energy 69, 59–63 (2013)

4. Erasmus, B., Van Heerden, F.A.: The Lattice Boltzmann Method Applied to Neutron Transport. U.S. Department of Energy Office of Scientific and Technical Information, Oak Ridge (2013)

5. Fernandes, J.C.L., Bodmann, B.E.J., Vilhena, M.T.: On multi-group neutron transport in planar one dimensional geometry: a solution for a localized pulsed source. Ann. Nucl. Energy 101, 552–558 (2017)

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