Radioactive decay chains, fission product poison burnup, point reactor kinetics with and without delayed neutrons. Neutron diffusion equation, criticality condition and critical size calculations.
Prerequisite: 231 and MATH 316.
{Spring}
Principles of Nuclear Engineering - CHNE 231
Applied Ordinary Differential Equations - MATH **316
MSC 11 6325
1 University of New Mexico
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