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NE 220

Course Title: 
Irradiation Effects in Nuclear Materials
Course Units: 
3
Catalog Description: 
  • Physical aspects and computer simulation of radiation damage in metals. Void swelling and irradiation creep. Mechanical analysis of structures under irradiation. Sputtering, blistering, and hydrogen behavior in fusion reactor materials. Offered odd-numbered years.
Course Prerequisite: 
  • NE 120 or consent of instructor
Course Objectives: 
  1. Basics of Radiation Damage - Collision dynamics; displacements; cross sections; dose(dpa); computer simulation of radiation damage due to neutrons.
  2. Ion interactions with solids - Monte Carlo method and the TRIM code;
  3. Point defect characteristics- equilibrium concentrations of vacancies and interstitials; diffusion of point defects; point defect reactions
  4. Extended Defects in Solids - bubbles and voids; dislocations
  5. Interaction of point defects and extended defects; diffusion of point defects to cavities and dislocations; interstitial bias of dislocations; point defect balances
  6. Void Swelling - nucleation and growth of voids; effect of gas pressure on swelling
  7. Irradiation and Thermal Creep - swelling-driven creep; SIPA creep
  8. Irradiation growth
  9. Structural Analysis under Irradiation - effects of temperature, swelling and creep
  10. Fusion Materials
  11. Heating and Vaporization of the First Wall
  12. Sputtering due to Heavy Ions
  13. Hydrogen Behavior in Metals
  14. Blistering of First Wall
Textbook(s) and/or Other Required Materials: 
  • D. R. Olander, "Fundamental Aspects of Nuclear Reactor Fuel Elements", U. S. Gov't. Printing Office (1976) (several copies in the Engineering Library)
Class/Laboratory Schedule: 
  • Three hours of lecture per week