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: 314 and MATH **316.
Restriction: admitted to School of Engineering.
{Fall}
Thermodynamics and Nuclear Systems - NE 314 [CHNE 314]
Applied Ordinary Differential Equations - MATH **316
MSC11 6325
1 University of New Mexico
Albuquerque, NM 87131
(505) 277-8900
Phone: (505) 277-6809
Fax: