Dr. K. L. Murty

Nuclear Engineering

Phone: 919-515-3657
Instructor Website

MSE 509 Nuclear Materials

3 Credit Hours

(also offered as NE 509)

In this course, most of the materials issues encountered in the operation of nuclear power reactors are discussed. The objective of the course is to give students a background in materials for nuclear power reactors and to discuss the unique changes that occur in these materials under the reactor environment, so that students understand the limitations put on reactor operations and reactor design by materials performance. In the first part of the course we review basic concepts of physical metallurgy to develop an understanding of the relationship between microstructure and material properties outside of irradiation. In the second part of the course, we describe the process of radiation-material interaction, present the methods to calculate atomic displacement damage produced by exposure to irradiation, and describe the changes in material properties that results from irradiation exposure. In the third part of the course, special attention is given to property changes affecting the fuel and cladding performance and operational safety such as corrosion of the cladding, hydriding, fuel expansion, Pellet-Cladding Interactions, stress corrosion-cracking; Credit will not be given for both NE/MSE 409 and NE/MSE 509.

Syllabus Lecture Videos Lecture Notes Course Website