Author/Authors :
Pozzi، نويسنده , , S.A. and Clarke، نويسنده , , S.D. and Walsh، نويسنده , , WJ and Miller، نويسنده , , E.C. and Dolan، نويسنده , , J.L. and Flaska، نويسنده , , M. and Wieger، نويسنده , , B.M. and Enqvist، نويسنده , , A. and Padovani، نويسنده , , E. and Mattingly، نويسنده , , J.K. and Chichester، نويسنده , , D.L. and Peerani، نويسنده , , P.، نويسنده ,
Abstract :
This paper describes the use of the Monte Carlo code MCNPX-PoliMi for nuclear-nonproliferation applications, with particular emphasis on the simulation of spontaneous and neutron-induced nuclear fission. New models for the outgoing neutrons and gamma rays emitted in spontaneous and induced fission are described. For spontaneous fission, the models include prompt neutron energy distributions that depend on the number of neutrons emitted in the individual fission events. For neutron-induced fission, due to lack of data, the prompt neutron energy distributions are independent of the number of neutrons emitted in the individual fission events. Gamma rays are sampled independently of the neutrons. Code validation is performed on well-characterized mixed-oxide fuel and plutonium-oxide samples.
Keywords :
Liquid scintillator , Mixed-oxide fuel , Nonproliferation , Plutonium oxide , MCNP , MCNPX-PoliMi
