PAPERS AND PRESENTATIONS

 

 

 

 

Publications

 

  1. T. R. Allen, L. Tan, G. S. Was, and E. A. Kenik, “Thermal and Radiation-Induced Segregation in Model Nickel-Based Alloys,” Journal of Nuclear Materials, 361, #2-3, 174-183 (2007).

 

  1. M. J. Hackett and G. S. Was, “Effects of Oversized Solute Additions on Radiation-Induced Segregation and SCC Susceptibility,” 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, T. R. Allen, J. Busby, and P. J. King, eds., Canadian Nuclear Society, Toronto (2007).

 

  1. Z. Jiao and G. S. Was, “The Role of Localized Deformation on IASCC of Proton-Irradiated Austenitic Stainless Steel,” 13th International Conference on Degradation of Materials in Nuclear Power Systems – Water Reactors, T. R. Allen, .J. Busby, and P. J. King, eds., Canadian Nuclear Society, Toronto (2007).

 

  1. Z. Jiao, J. T. Busby, and G. S. Was, “Deformation Microstructure of Proton-Irradiated Stainless Steels,” Journal of Nuclear Materials, 361, 2-3, 218-227 (2007).

 

  1. Z. Jiao, A. N. Ham, and G. S. Was, “Microstructure of Helium-Implanted and Proton-Irradiated T91 Ferritic/Martensitic Steel,” Journal of Nuclear Materials, 367-370, part 1, 440-445 (2007).

 

  1. A. Serres, L. Fournier, and G. S. Was, “Radiation Induced Microstructure, Strain Localization and Iodine-Induced Stress Corrosion Cracking in Proton Irradiated Zircaloy 4,” 13th International Conference on Degradation of Materials in Nuclear Power Systems – Water Reactors, T. R. Allen, J. Busby, and P. J. King, eds., Canadian Nuclear Society, Toronto (2007).

 

    G. S. Was, Z. Jiao, and J. T. Busby, “Recent Developments in Understanding the Mechanism of IASCC,” Proceedings of the International Symposium on Research for Aging Management of Light Water Reactors, Institute for Nuclear Safety Systems, Inc, Fukui, Japan, 8-1 to 8-23 (2007).

 

    E. A. West, S. Teysseyre, Z. Jiao, and G. S. Was, “Influence of Irradiation Induced Microstructure on the Stress Corrosion Cracking Behavior of Austenitic Alloys in Supercritical Water,” Proceedings of the 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems (2007).

 

     
     

    Presentations

     

    1. M. J. Hackett, J. T. Busby, R. Najafabadi, and G. S. Was, “Mechanism of Zr and Hf in Reducing Radiation-Induced Segregation in 316SS,” The 6th Pacific Rim International Conference on Advanced Materials and Processing, Korean Institute of Metals and Materials, Jeju Island, South Korea, November 2007.
    2. M. J. Hackett, J. T. Busby, and G. S. Was, “Mechanism of Zr and Hf in Reducing Radiation-Induced Segregation in 316SS,” TMS Annual Meeting, Orlando, FL, February 2007.
    3. M. J. Hackett and G. S. Was, “Mechanism of Zr and Hf in Reducing Radiation-Induced Segregation in 316SS,” Poster Presentation, TMS Annual Meeting, Orlando, FL, February 2007.
    4. Z. Jiao and G. S. Was, “IASCC Initiation and Localized Deformation in Austenitic Stainless Steels,” TMS Annual Meeting, Orlando, FL, February 2007.