This course is intended to give graduate students in Nuclear Engineering and in Materials Science a background on the special materials problems that occur in nuclear power reactors. Materials in nuclear reactors are subjected to an unusually harsh environment in which high temperatures, a corrosive medium and neutron irradiation damage, combine to cause the materials to fail to perform their design function. This degradation of materials in reactor environments has great economic consequences for the utilities that operate the reactors, and could potentially have safety implications as well. There is thus a great driving force to better understand the mechanisms of materials degradation in nuclear power reactors, specially the synergistic effects of radiation and electrochemistry which are at the root of phenomena such as irradiation assisted stress corrosion cracking.
The course is cross-listed in Nuclear Engineering and Materials Science, and is jointly taught by professors from both, with the idea that an interdisciplinary approach can help develop a mechanistic understanding of these complex phenomena. Whenever possible we will present simple mathematical models to illustrate the nature of the processes, while keeping in mind the full complexity present in the real cases. The aim is to teach the fundamentals of radiation damage, electrochemistry and materials behavior, and apply them all together to the study of specific degradation mechanisms, evaluating the degree of degradation, and quantitatively modeling the processes.
At the end of the course, the students should have accomplished the following educational objectives: