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 - NONE 231
Applied Ordinary Differential Equations - MATH **316
MSC11 6325
1 University of New Mexico
Albuquerque, NM 87131
(505) 277-8900
Phone: (505) 277-6809
Fax: