Publications

Radiation Materials Science Research Group/Publications

Papers and Presentations

The Radiation Materials Science Group publishes results from the different research projects in a number of different locations. Complete citations for the most recent publications are listed below. Due to copyright issues, we cannot provide the entire journal. If you would like to receive a reprint of an article, please contact the lead author (via the link provided). Thank you!

2007

Books/Chapters in Books

  • Radiation Damage from Different Particle Types,” G. S. Was and T. R. Allen, Radiation Effects in Solids, NATO Science Series II: Mathematics, Physics and Chemistry, Vol. 235, Sickafus, Kurt E.; Kotomin, Eugene A.; Uberuaga, Blas P. (Eds.), Springer, Berlin, 2007, pp. 65-98.
  • Radiation-Enhanced Diffusion and Radiation-Induced Segregation,” T. R. Allen and G. S. Was, Radiation Effects in Solids, NATO Science Series II: Mathematics, Physics and Chemistry, Vol. 235, Sickafus, Kurt E.; Kotomin, Eugene A.; Uberuaga, Blas P. (Eds.), Springer, Berlin, 2007, pp. 123-152.
  • Role of Irradiation in Stress Corrosion Cracking,” G. S. Was, Radiation Effects in Solids, NATO Science Series II: Mathematics, Physics and Chemistry, Vol. 235, Sickafus, Kurt E.; Kotomin, Eugene A.; Uberuaga, Blas P. (Eds.), Springer, Berlin, 2007, pp. 421-448.

Journal Articles

  • Q. J. Peng, S. Teysseyre, P. L. Andresen and G. S. Was, “Stress Corrosion Crack Growth in 316 Stainless Steel in Supercritical Water,” Corrosion, 63 (2007) 1033-1041.
  • G. S. Was, P. Ampornrat, G. Gupta, S. Teysseyre, E. A. West, T. R. Allen, K. Sridharan, L. Tan, Y. Chen, X. Ren and C. Pister, “Corrosion and Stress Corrosion Cracking in Supercritical Water,” J. Nucl. Mater. 371 (2007) 176-201.
  • S. Teysseyre, Z. Jiao, E. West, G.S. Was, “Effect of Irradiation on Stress Corrosion Cracking In Supercritical Water,” J. Nucl. Mater. 371 (2007) 107-117.
  • S. Teysseyre, Q. Peng, C. Becker and G.S. Was, “Facility for Stress Corrosion Cracking of Irradiated Specimens in Supercritical Water,” J. Nucl. Mater. 371 (2007) 98-106.
  • P. Ampornrat, G. S. Was, “Oxidation of Ferritic-Martensitic Alloys T91, HCM12A and HT-9 in Supercritical Water,” J. Nucl. Mater. 371 (2007) 1-17.
  • A. Motta, A. Yilmazbayhan, M. Gomes da Silva, R. J. Comstock, G. S. Was, J. T. Busby, E. Gartner, Q. Peng, Y. Hwan Jeong, J. Yong Park, Zirconium Alloys for Supercritical Water Reactor Applications: Challenges and Possibilities,” J. Nucl. Mater. 371 (2007) 61-75.
  • Z. Jiao, N. Ham and G. S. Was, “Microstructure of He-implanted and Proton-irradiated T91 Ferritic-Martensitic Steel,” J. Nucl. Mater. 367-370 (2007) 440-445.
  • G. S. Was, “Materials Degradation in Fission Reactors: Lessons Learned of Relevance to Fusion Reactor Systems,” J. Nucl. Mater. 367-370 (2007) 11-20.
  • B. M. Capell and G. S. Was, “Selective Internal Oxidation as a Mechanism for Intergranular Stress Corrosion Cracking of Ni-Fe-Cr Alloys,” submitted to Metall. Trans. A, 38A (2007) 1244-1259.
  • Q. Peng, E. Gartner, J. T. Busby, A. T. Motta and G. S. Was “Corrosion Behavior of Model Zirconium Alloys in Deaerated Supercritical Water at 500„aC,” Corrosion, 63 (6) (2007) 577-590.
  • Z. Jiao, J. T. Busby and G. S. Was, “Deformation Microstructure of Proton-Irradiated Stainless Steels,” J. Nucl. Mater. 361 #2-3 (2007) 218-227.
  • T. R. Allen, L. Tan, G. S. Was and E. A. Kenik, “Thermal and Radiation-Induced Segregation in Model Nickel-Based Alloys,” J. Nucl. Mater. 361 #2-3 (2007) 174-183.
  • G. Gaurav, P. Ampornrat, X. Ren, K. Sridharan, T. R. Allen and G. S. Was, “Role of Grain Boundary Engineering on the SCC Behavior of F-M Alloy HT-9, J. Nucl. Mater. 361 #2-3 (2007) 160-173.
  • G. S. Was and P. L. Andresen, “Stress Corrosion Cracking Behavior of Alloys in Aggressive Nuclear Reactor Core Environments,” Corrosion, 63 #1 (2007) 19-45.

Conference Papers

  • 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 (2007) 8-1 to 8-23.
  • G. S. Was and B. M. Capell, “Selective Internal Oxidation in Ni-Cr-Fe Alloys during Exposure in Hydrogenated Steam,” 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.
  • 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” 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.
  • S. Teysseyre and G. S. Was, “Stress Corrosion Cracking of Neutron Irradiated Steel in Supercritical Water,” 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.
  • M. J. Hackett and G. S. Was, “Effect of Oversized Solutes in 316SS on Radiation Induced Segregation and SCC Susceptibility,” 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.
  • 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.
  • 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.
  • T. R. Allen and G.S. Was, “Novel Techniques to Mitigate Corrosion and Stress Corrosion Cracking in Supercritical Water,” Corrosion 2007, Paper 07RTS9, NACE International, Houston, TX, 2007.

2006

Books/Chapters in Books

  • G. S. Was, J. T. Busby and P. L. Andresen, “Effect of Irradiation on Stress Corrosion Cracking and Corrosion in Light Water Reactors,” Corrosion in the Nuclear Industry, in Corrosion: Environments and Industries, ASM Handbook, ASM International, 13C, 386-414 (2006).

Journal Articles

  • B. Alexandreanu and G. S. Was, “The Role of Stress in the Efficacy of Coincident Site Lattice Boundaries in Improving Creep and Stress Corrosion Cracking,” Scripta Materialia, 54, 1047- 1052 (2006). (Invited)
  • T. R. Allen, L. Tan, J. D. Tucker, J. Gan, G. Gupta, G. S. Was, S. Shutthanandan and S. Thevuthasan, “Microstructural Development in Advanced Ferritic-Martensitic Steel HCM12A,” Journal of Nuclear Materials, 351, 1-3, 174-186 (2006).
  • G. Gupta, Z. Jiao, A. N. Ham, J. T. Busby and G. S. Was, “Microstructural Evolution of Proton Irradiated T91,” Journal of Nuclear Materials, 351, 1-3, 162-173 (2006).
  • S. Teysseyre and G. S. Was, “Stress Corrosion Cracking of Austenitic Alloys in Supercritical Water,” Corrosion, 62, 12, 1100-1116 (2006).
  • G. S. Was, S. Teysseyre and Z. Jiao, “Corrosion of Austenitic Alloys in Supercritical Water,” Corrosion, 62, 11, 989-1005 (2006).

Conference Papers

  • G. S. Was, “Cladding Performance Issues Relevant to a Fueled Test Loop for the SCWR,” Workshop on Fueled Loop Tests for SCWR R amd D, NEA, Paris, March 2006.
  • S. Teysseyre, Z. Jiao, *E. West and G. S. Was, “Effect of Irradiation on Stress Corrosion Cracking In Supercritical Water,” 2006 ANS Annual Meeting, Reno, NV, June 2006.
  • S. Teysseyre, Q. Peng, C. Becker and G. S. Was, “Facility for Stress Corrosion Cracking of Irradiated Specimens in Supercritical Water,” 2006 ANS Annual Meeting, Reno, NV, June 2006.
  • G. S. Was, “Corrosion and Stress Corrosion Cracking of Alloys for Supercritical Water Reactor Core Components,” SCWR Review Workshop, KAPL, Albany, March 2006.
  • G. S. Was, “Ion Irradiation for the Study of Neutron Irradiation Damage,” Conference on Accelerator Applications in Research and Industry, Fort Worth, TX, August 2006. (Invited)
  • G. S. Was, “Localized Deformation Processes in IGSCC and IASCC,” International Cooperative Group – Environmental Assisted Cracking, Charleston, SC, April 2006.
  • G. S. Was, J. T. Busby and Z. Jiao, “Contribution of Localized Deformation to IGSCC and IASCC,” Proceedings of the 16th European Conference of Fracture, paper #509, edited by E. E. Gdoutos, Springer, Berlin, 2006.

2005

Books/Chapters in Books

  • T. R. Allen, J. I. Cole, J. Gan, G. S. Was, *R. Dropek and E. A. Kenik, “Swelling and Radiation-Induced Segregation in Austenitic Alloys,” Journal of Nuclear Materials, 341, 90-100 (2005).
  • T. R. Allen, L. Tan, *J. D. Tucker, J. Gan, *G. Gupta, G. S. Was, S. Shutthanandan and S. Thevuthasan, “Radiation Resistance of Advanced Ferritic-Martensitic Steel HCM12A,”Journal ASTM International, 2, No. 8 (2005).
  • J. T. Busby, M. C. Hash, and G. S. Was, “The Relationship Between Hardness and Yield Stress in Irradiated Austenitic and Ferritic Steels,” Journal of Nuclear Materials, 336, 267-278 (2005).
  • J. T. Busby, *M. M. Sowa, G. S. Was and E. P. Simonen, “Post-Irradiation Annealing of Small Defect Clusters,” Philosophical Magazine, 85, #4-7, 609-617 (2005).
  • G. Gupta and G. S. Was, “Interpretation of Improved Creep Properties of a 9Cr-1Mo-Nb-B (T91) steel by Grain Boundary Engineering,” TMS Letters, 2, No. 3, 71-72 (2005).
  • G. Gupta and G. S. Was, “The Role of Grain Boundary Engineering on the High Temperature Creep of Ferritic-Martensitic Alloy T-91,” Journal ASTM International, 2, No. 3 (2005).
  • M. J. Hackett, G. S. Was, and E. P. Simonen, “Modeling the Effects of Oversize Solute Addition in Radiation-Induced Segregation in Austenitic Stainless Steel,” Journal ASTM International, 2, No. 7 (2005).
  • B. H. Sencer, G. S. Was, H. Yuya, Y. Isobe, M. Sagasaka and F. A. Garner, “Cross-sectional TEM and X-ray Examination of Radiation-Induced Stress Relaxation of Peened Stainless Steel Surfaces, “Journal of Nuclear Materials, 336, 314-322 (2005).
  • G. S. Was and J. T. Busby, “Role of Irradiated Microstructure and Microchemistry in Irradiation Assisted Stress Corrosion Cracking,” Philosophical Magazine, 85, No. 4-7, 443- 465 (2005).
  • G. S. Was, M. Hash and G. R. Odette, “Proton Irradiation of Model and Commercial Pressure Vessel Steels,” Philosophical Magazine, 85, No. 4-7, 703-722 (2005).
  • X. T. Zu, K. Sun, M. Atzmon, L. M. Wang, L. P. You, F. R. Wan, J. T. Busby, G. S. Was and R. B. Adamson, “Effect of Proton and Ne Irradiation on the Microstructure of Zircaloy 4,” Philosophical Magazine, 85, 649-659 (2005).

Conference Papers

  • T. R. Allen, L. Tan, Y. Chen, X. Ren, K. Sridharan, G. S. Was, *G. Gupta and P. *Ampornrat, “Corrosion of Ferritic-Martensitic Alloys in Supercritical Water for GenIV Application,” Proceedings of Global 2005, Paper 419, Tsukuba, Japan Oct. 9-13 (2005).
  • T. R. Allen, L. Tan, Y. Chen, K. Sridharan, M. T. Machut, J. Gan, *G. Gupta, G. S. Was and S. Ukai, “Corrosion and Radiation Response of Advanced Ferritic-Martensitic Steels for Generation IV Application,” Proceedings of Global 2005, Paper IL001, Tsukuba, Japan Oct. 9- 13 (2005).
  • P. Ampornrat, C. B. Bahn and G. S. Was, “Corrosion and Stress Corrosion Cracking of Ferritic-Martensitic Alloys in Supercritical Water,” 12th International Conference on Degradation of Materials in Nuclear Power Systems – Water Reactors, The Minerals, Metals and Materials Society, Salt Lake City, UT, August 14-18, 2005.
  • P. Ampornrat, *G. Gupta and G. S. Was, “Corrosion and SCC of Ferritic-Martensitic Steels in Supercritical Water,” Transactions of the American Nuclear Society, 92, 117-118 (2005).
  • J. T. Busby and G. S. Was, “Effect of Metallurgical Conditions on Irradiation-assisted Stress Corrosion Cracking of Commercial Stainless Steels,” 12th International Conference on Degradation of Materials in Nuclear Power Systems – Water Reactors, The Minerals, Metals and Materials Society, Salt Lake City, UT, August 14-18, 2005.
  • G. Gupta and G. S. Was, “Effect of Proton Irradiation and Grain Boundary Engineering on Stress Corrosion Cracking of Ferritic-Martensitic Alloys in Supercritical Water,” 12th International Conference on Degradation of Materials in Nuclear Power Systems – Water Reactors, The Minerals, Metals and Materials Society, Salt Lake City, UT, August 14-18, 2005.
  • M. J. Hackett and G. S. Was, “The Effect of Oversize Solute Additions on the Irradiation- Assisted Stress Corrosion Cracking of Austenitic Stainless Steels,” 12th International Conference on Degradation of Materials in Nuclear Power Systems – Water Reactors, The Minerals, Metals and Materials Society, Salt Lake City, UT, August 14-18, 2005.
  • Y. H. Jeong, J. Y. Park, H. G. Kim, J. T. Busby, *E. Gartner, M. Atzmon, G. S. Was, R. J. Comstock, Y. S. Chu, M. Gomes da Silva, A. Yilmazbayhan and A. T. Motta, “Corrosion of Zirconium-Based Fuel Cladding Alloys in Supercritical Water,” 12th International Conference on Degradation of Materials in Nuclear Power Systems – Water Reactors, The Minerals, Metals and Materials Society, Salt Lake City, UT, August 14-18, 2005.
  • Z. Jiao, J. T. Busby, R. Obata and G. S. Was, “Influence of Localized Deformation on Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated Austenitic Alloys,” 12th International Conference on Degradation of Materials in Nuclear Power Systems – Water Reactors, The Minerals, Metals and Materials Society, Salt Lake City, UT, August 14-18, 2005.
  • G. S. Was and T. R. Allen, “Time, Temperature and Dissolved Oxygen Dependence of Oxidation of Austenitic and Ferritic-Martensitic Alloys in Supercritical Water,” Proceedings of ICAPP 2005, American Nuclear Society, paper #5690, Seoul, S. Korea, May 15-19, 2005.
  • G. S. Was and P. L. Andresen, “Stress Corrosion Cracking of Alloys in Aggressive Nuclear Reactor Core Environments,” NACE International Annual Conference, Corrosion 2005, paper #05RTS5, Houston, TX, April 3-7, 2005.
  • G. S. Was and S. Teysseyre, “Challenges and Recent Progress in Corrosion and Stress Corrosion Cracking of Alloys for Supercritical Water Reactor Core Components,” Proceedings of the 12th International Conference on the Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, American Nuclear Society, 1343-1357, Salt Lake City, UT, August 14-18, 2005.
  • G. S. Was, S. Teysseyre, Z. Jiao and *J. McKinley, “Oxidation and Stress Corrosion Cracking of Austenitic Alloys in Supercritical Water,” NACE International Annual Conference, Corrosion 2005, paper #05397, Houston, TX, April 3-7, 2005.

2004

Books/Chapters in Books

  • G. S. Was, L. Nelson, and P. King, eds, Eleventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, American Nuclear Society, La Grange Park, IL (2004).

Journal Articles

  • J. Gan, E. P. Simonen, S. M. Bruemmer, L. Fournier, B. H. Sencer, and G. S. Was, “The Effect of Oversized Solute Additions on the Microstructure of 316SS Irradiated with 5 MeV Ni++ Ions or 3.2 MeV Protons,” J. Nucl. Mater., 325, 94-106 (2004).
  • G. Gupta, *B. Alexandreanu, and G. S. Was, “Grain Boundary Engineering of Ferritic- Martensitic Alloy T91,” Metall. Trans. A, 35A, 717-719 (2004).
  • G. S. Was, *B. Alexandreanu, and *J. Busby, “Localized Deformation Induced IGSCC and IASCC of Austenitic Alloys in High Temperature Water,” Key Engin. Mat’ls., 261-263, 885- 902 (2004).
  • X. T. Zu, M. Atzmon, L. M. Wang, L. P. You, F. R. Wan, G. S. Was, and R. B. Adamson, “Effect of Ion Irradiation on Microstructure and Hardness of Zircaloy-4,” J. ASTM International, 1, JAI11316 (2004).

Conference Papers

  • J. T. Busby and G. S. Was, “Irradiation Assisted Stress Corrosion Cracking in Model Austenitic Alloys with Solute Additions,” Proc. 11th Int’l Conf. Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, 995-1014, American Nuclear Society, LaGrange Park, IL (2004).
  • J. T. Busby, *M. M. Sowa, and G. S. Was, “The Role of Fine Defect Clusters in Irradiation- Assisted Stress Corrosion Cracking of Proton-Irradiated 304 Stainless Steel,” Effects of Radiation on Materials: 21st International Symposium, ASTM STP, 78-91, edited by M. L. Grossbeck, T. R. Allen, R. G. Lott, and A. S. Kumar, American Society for Testing and Materials, West Conshohocken, PA (2004).
  • J. I. Cole, T. R. Allen, G. S. Was, and E. A. Kenik, “The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys,” Effects of Radiation on Materials: 21st International Symposium, ASTM STP, 540-552, edited by M. L. Grossbeck, T. R. Allen, R. G. Lott and A. S. Kumar, American Society for Testing and Materials, West Conshohocken, PA (2004).
  • R. B. Dropek, G. S. Was, J. Gan, J. I. Cole, T. R. Allen, and E. A. Kenik, “Bulk Composition and Grain Boundary Engineering to Improve Stress Corrosion Cracking Behavior of Proton Irradiated Stainless Steels,” Proc.11th Int’l Conf. Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, 1132-1141, American Nuclear Society, La Grange Park, IL (2004).
  • M. C. Hash, L. M. Wang, *J. T. Busby, and G. S. Was, “The Effect of Hardening Source in Proton Irradiation-Assisted Stress Corrosion Cracking of Cold-Worked Type 304 Stainless Steel,” Effects of Radiation on Materials: 21st International Symposium, ASTM STP, 92-104, edited by M. L. Grossbeck, T. R. Allen, R. G. Lott, and A. S. Kumar, American Society for Testing and Materials, West Conshohocken, PA (2004).
  • Y. Isobe, M. Sagisaka, B. H. Sencer, G. S. Was, F. A. Garner, H. Yuya, A. Nishikawa, and Y. Sugita, “Proton-Induced Relaxation of Surface Stresses Resulting from Heavily Cold-Worked 304 Stainless Steels,” Proc. 11th Int’l Conf. Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, 930-939, American Nuclear Society, La Grange Park, IL (2004).
  • B. H. Sencer, G. S. Was, L. Fournier, E. Kenik, and S. Bruemmer, “Influence of Oversized Solute Additions on Radiation-Induced Microstructure and Microchemistry in Austenitic Stainless Steel,” Effects of Radiation on Materials: 21st International Symposium, ASTM STP, 46-55, edited by M. L. Grossbeck, T. R. Allen, R. G. Lott, and A. S. Kumar, American Society for Testing and Materials, West Conshohocken, PA (2004).
  • S. Teysseyre, J. McKinley, G. S. Was, D. B. Mitton, H. Kim, J-K Kim, and R. M. Latanision, “Corrosion and Stress Corrosion Cracking of Austenitic Alloys in Supercritical Water,” Proc. 11th Int’l Conf. Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, 63-72, American Nuclear Society, La Grange Park, IL (2004).
  • G. S. Was, “Recent Developments in Understanding Irradiation Assisted Stress Corrosion Cracking,” Proc. 11th Int’l Conf. Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, 965-985, American Nuclear Society, La Grange Park, IL, (2004).
  • G. S. Was, *B. Alexandreanu, P. Andresen, and M. Kumar, “Role of Coincident Site Lattice Boundaries in Creep, Corrosion and Stress Corrosion Cracking,” Proc. Materials Research Society, 87-100, Materials Research Society, Warrendale, PA (2004).
  • G. S. Was, *J. T. Busby, T. R. Allen, and J. Gan, “Assessment of Materials for Accelerator Applications Using Proton Irradiation,” Proc. Sixth Int’l Meeting on Nuclear Applications of Accelerator Technology (AccApp’03), 864-873, American Nuclear Society, La Grange Park, IL (2004).
  • G. S. Was, S. Teysseyre, and J. McKinley, “Corrosion and Stress Corrosion Cracking of Iron and Nickel-base Austenitic Alloys in Supercritical Water,” Proc. NACE Annual Conference, Corrosion 2004, paper #04492, New Orleans, LA (2004).