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NE 723 Neutron Transport Theory

±··¡Ìý723ÌýÌýNeutron Transport TheoryÌýÌý(3 credit hours)ÌýÌý

Advanced theory of neutron transport and computational methods of solving particle transport (linear Boltzmann) equation for reactor physics problems. Principle topics: models of neutron transport; analytic methods for solving transport equation; asymptotic diffusion limit; PN and SPN methods, homogenization methodology; numerical methods for multidimensional problems; computational methods for multiphysics problems. Objective is to enable students to read literature and perform relevant analysis of neutron transport and reactor-physics problems.

Typically offered in Fall only