Courses Fall 2023
NUC ENG 3205 Fundamentals of Nuclear Engineering
An introduction to the principles and equations used in nuclear fission reactor technology including: reactor types; neutron physics and reactor theory; reactor kinetics and control; radiation protection; reactor safety and licensing; and environmental aspects of nuclear power.
NUC ENG 4207 / 5207 Nuclear Fuel Cycle
Nuclear fuel reserves and resources; milling, conversion, and enrichment; fuel fabrication; in-and-out-of core fuel management; transportation, storage, and disposal of nuclear fuel; low level and high level waste management; economics of the nuclear fuel cycle.
NUC ENG 4253 Monte Carlo Approach to Reactor Analysis
An introduction to a stochastic method for solving particle transport problems with a view to utilize the method in reactor design and analysis, shielding problems, flux calculations, reaction rates determination and general steady state reactor physics analysis.
Courses Spring 2024
NUC ENG 6203 Advanced Reactor Physics
Transport and diffusion theory; multigroup approximation; criticality calculations; cross-section processing; buildup and depletion calculations; delayed neutrons and reactor kinetics; lattice physics calculations; full core calculations; analysis and measurement of reactivity coefficients.
NUC ENG 4497 Nuclear System Design II
A complete design of a nuclear system (e.g.a fission or fusion nuclear reactor plant, a space power system, a radioactive waste disposal system).