Nuclear Reactor Theory
NE 510 / 410 (3)Neutron transport equation, differential scattering cross section, diffusion approximation, one group diffusion theory including green’s function and eigenfunction expansion, Breit-Wigner formula, slowing down theory, reactor kinetics, multigroup methods, topics selected from numerical methods for reactor analysis.
Prerequisite: 315.
Prerequisites / Corequisites
Nuclear Engineering Analysis and Calculations - NE 315
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