Research in the Radiation Materials Science group is supported through a number of different projects:
- A Mechanistic Basis for Irradiation Assisted Stress Corrosion Cracking
- Accelerator-Based Study of Irradiation Creep of Pyrolytic Carbon Used in TRISO Fuel Particles for Very High Temperature Reactors (VHTR)
- Acquisition of a Research Grade Ion Implanter for Research and Education in Ion Beam Modification of Materials
- Alloys for 1000°C Service in the Next Generation Nuclear Plant
- BWRVIP Highly Irradiated Stainless Steel Crack Growth
- Candidate Materials Evaluation for the Supercritical Water-Cooled Reactor
- Consortium on Cladding and Structural Materials for Advanced Nuclear Energy Systems
- Constant Extension Rate Testing of Alloy 690 in Supercritical Water
- High Temperature Materials for the Gas-Cooled Fast Reactor
- Localized Deformation as a Primary Cause of Irradiation Assisted Stress Corrosion Cracking
- Radiation-Induced Segregation and Phase Stability in Candidate Alloys for the Advanced Burner Reactor
- Stress Corrosion Cracking and Corrosion of Candidate Alloys for the Supercritical Water Reactor Concept
- Stress Corrosion Cracking of Neutron Irradiated Cast Stainless Steels in High Temperature Water