Mr. Bradley C. Benefiel

Post Doctoral Research Associate
Idaho National Laboratory
Fuel Performance, Development and Qualification
Idaho Falls, ID
USA 83402

Papers:

A Comprehensive Study of AA 6061 Thermal Creep Models and their Effect on Residual Stress Predictions in Irradiated U-10Mo Fuel Plates
Remote-Handling Residual Stress Measurements for Non-irradiated and Irradiated Monolithic U-10Mo Nuclear Reactor Fuel Plates
Measurement of post-irradiation stress in irradiated monolithic U-10Mo fuel plates in a shielded Argon hot-cell environment