Nuclear Reactor Theory I
NONE *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: 314 and MATH 316
{Fall}
Prerequisites / Corequisites
Thermodynamics and Nuclear Systems - NONE 314
Applied Ordinary Differential Equations - MATH **316
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