Ben Hauch, Jacob Sager, Alex Mairov, Ben Maier, Clarissa Yablinsky and Kumar Sridharan attended MS&T 2013 from October 07-11, 2012 in Pittsburgh, PA. Ben Hauch presented the work being performed with 5083 Aluminum Alloys for corrosion resistance in salt-water environments using the cold spray deposition process. Kumar Sridharan chaired a session in the Materials Development for Nuclear Applications and ExtremeEnvironments symposium. Alex presented his work on the radiation and oxidation of thin film interfaces for use in future generation nuclear reactors as part of the Materials Development for Nuclear Applications and ExtremeEnvironments symposium. Additionally, Ben Maier presented research on the effects of proton irradiations on ZrCx with various stoichiometries at 800 °C as part of this nuclear materials symposium as well. Jacob Sager discussed his work on the electrochemical and thermal properties of rare-earth chlorides in molten LiCl-KCl for processing of spent nuclear fuel. Congratulations to all attendees and presenters!
Yina Huang presented "Effects of proton irradiation on Zirconium Carbide with different stoichiometry" at the All Hands meeting.
On September 25th and 26th, 2012, we hosted the Fuel Aging in Storage and Transportation - Integrated Research Project (FAST-IRP) review meeting at the University of Wisconsin, Madison. The meeting was attended by lead researchers and engineers from across the United States. Attendees included faculty and students from five other universities performing research in this area and representatives from national laboratories, Department of Energy, and the Nuclear Regulatory Commission who are actively involved in the National Used Fuel Disposition Campaign and Fuel Cycle Research and Development program.
FAST IRP is a consortium of six universities (University of Wisconsin, Texas A&M University, North Carolina State University, Boise State University, University of Florida, and the University of Illinois) that are jointly working to address critical research gaps in the long-term storage of used nuclear fuel. A panel of national laboratory members provides technical guidance to the consortium and assists in aligning the consortium's research activities with the broader national programs. Among the areas of research being undertaken by the consortium are long term corrosion and stress corrosion cracking of canisters, delayed hydride cracking and creep of used zirconium alloy claddings, and sensors for monitoring of used fuel storage systems.