Ab initio simulation of radiation damage in nuclear reactor pressure vessel materials

POSTER

Abstract

Using Kinetic Monte Carlo we developed a code to study point defect hopping in BCC metallic alloys using energetics and attempt frequencies calculated using VASP, an electronic structure software package. Our code provides a way of simulating the effects of neutron radiation on potential reactor materials. Specifically we will compare the Molybdenum-Chromium alloy system to steel alloys for use in nuclear reactor pressure vessels.

Authors

  • Daniel Watts

    • U.S. Naval Academy
  • Daniel Finkenstadt

    • U.S. Naval Academy
    • U.S. Naval Academy, Physics Dept., Annapolis, MD
    • U.S. Naval Academy, Physics Department