ME 136N, Introduction to Nuclear and Radiation Engineering Concepts This course is intended to introduce students at all levels and from all disciplines on the many different aspects and applications of nuclear and radiation engineering/physics. Topics covered include: history of nuclear development, basic concepts of radiation and radioactivity, radioactive waste management, global warming and the impact of nuclear power plants, industrial applications, health physics, nuclear medicine, job opportunities at power plants, graduate school, and national laboratories.
ME 338C, Nuclear Power Engineering Fundamental principles of the design and analysis of nuclear systems; introduction to the physics of nuclear reactions, chain reactions, and nuclear energy generation; heat generation and conduction within nuclear systems; heat transfer and fluid flow in nuclear systems; the thermodynamics of nuclear power; the nuclear fuel cycle; and issues related to the materials aspect of reactor engineering. Prerequisites: Graduate standing.
ME 338D, Nuclear Reactor Theory I Principle concepts in the physics of nuclear systems; radiation, radioactive decay, and the buildup and depletion of isotopes in nuclear systems; neutron-nucleus interactions and nuclear cross sections; transport or radiation using one-group and two-group diffusion theory; concepts of criticality and time-dependent reactors.
ME 388H, Nuclear Safety and Security Probalistic Risk Assessment models and nuclear non=proliferation. Failure classifications, failure modes, effects, and criticality analysis (FMECA), fault and event trees, reliability block diagrams. Specific areas from the Code of Federal Regulations will be discussed such as 10 CFR 73, 74, 75. Prerequisite: Graduate standing. ME 388J, Neutron Interactions and their Apps in Nuclear Science and Engineering The fundamental principles of neutron interactions with matter and how these interactions are used in a variety of science and engineering research areas. Includes the history of neutron research, fundamental principles, dosimetry, depth profile, radiography, activation analysis, detection, homeland security, and scattering, with a significant emphasis placed on experimental design of these neutron techniques. Prerequisite: Graduate standing.
ME 388M, Mathematical Methods for Nuclear and Radiation Engineers Fundamental mathematics necessary for graduate studies in nuclear and radiation engineering. The topics include statistics, experimental data, propagation of error, detection limits, differential and partial differential equations encountered in graduate level nuclear and radiation engineering courses. Both time dependent and space dependent solutions will be covered.
ME 388P, Applied Nuclear Physics An introduction to basic physics that underlies all applied nuclear systems. Properties of the nucleus and its structure. Binding energy and nuclear stability, liquid drop model of the nucleus. The shell model of the nucleus, deuteron bound-state wave function and energy, n-p scattering cross section, transition probability per unit time and barrier transmission probability. Nuclear conservation laws. The energetics and general cross section behaviour in nuclear reactions. Interactions of charged particles, neutrons, and gamma rays with matter. Alpha, beta and gamma decay. Examples are drawn from nuclear reactor engineering, nuclear medicine and environmental science. Prerequisites: Graduate standing.
ME 388S, Modern Trends in Nuclear and Radiation Engineering Student presentations on current research topics in nuclear and radiation engineering outside their research; techniques in proposal writing. Prerequisite: Graduate standing.
ME 389C, Nuclear Environmental Protection Course is designed to provide fundamental understanding of ionizing radiation and its interactions with matter and living tissues, radioactivity decay kinetics, external and internal dose measurement, transportation, the environment, managing radioactive waste streams, and safeguards. Prerequisites: Graduate Standing.
ME 389F, The Nuclear Fuel Cycle A survey of the nuclear fuel cycle, including resource acquisition, fuel enrichment and fabrication, spent fuel reprocessing and repository disposal. Nuclear fuel management and reactor physics are addressed in the context of fuel burn-up calculations. Uses cross-disciplinary tools such as cost-benefit and environmental impact analyses. Includes fuel cycles currently in use, advanced fuel cycle concepts currently being presented in the technical literature, and a group project designed to research, analyze, and document the technical, economic, and/or environmental ramifications of one of these advanced fuel cycles. Prerequisite: Graduate standing.
ME 390T, Nuclear and Radiochemistry An introduction to the theory and applications of nuclear and radiochemistry. One lecture per week and one three hour laboratory. Lecture and laboratory topics include alpha, beta, and gamma ray processes; fission products; statistics; solvent extraction; absorption and leaching techniques; various counting methods; and radiation protection.