ENU 4001-Nuclear Engineering Analysis 1

Continuous and discrete variable solution methods for the statistical, algebraic, differential, and integral equations important in nuclear engineering.  Problems involving neutron, photon, fluids, and temperature distributions in configuration, time and velocity are mathematically modeled, solved, and interpreted. Using the book Foundations in Applied Nuclear Engineering Analysis by Glenn Sjoden, note that there is a 2nd edition out now!

ENU5615C  – Nuclear Radiation Detection and Instrumentation

Interaction of radiation with matter, radiation-detection systems, pulse shaping, amplification, amplitude and time-analyzing circuitry; counting and measuring devices and control systems for nuclear reactors. Using the book: Radiation Detection and Measurement by Glenn F. Knoll (4th Ed.).

ENU 6106 – Nuclear Reactor Analysis I

Nuclear criticality, neutron transport equation, multigroup neutron diffusion theory, and perturbation theory. Reactor kinetics: point model, reactivity feedback, and space-time models. Using the book Nuclear Reactor Analysis by J. Duderstadt, & L. Hamilton