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Nuclear Reactor Theory I

CHNE *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}

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Prerequisites / Corequisites

Thermodynamics and Nuclear Systems - CHNE 314

Applied Ordinary Differential Equations - MATH **316

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