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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.
Restriction: admitted to School of Engineering.
Nuclear Engineering Analysis and Calculations - NE 315
MSC11 6325
1 University of New Mexico
Albuquerque, NM 87131
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