Kale Stephenson
Kale J. Stephenson, Ph.D.
Associate
Materials & Corrosion Engineering
  • Menlo Park

Dr. Stephenson specializes in failure analysis, materials science, metallurgy, fracture, fatigue, environmentally-induced cracking, and material irradiation effects. He has performed extensive experimental laboratory work and is also experienced with finite element modeling. While his interests are focused on metals, they extend to other material systems such as well.  Dr. Stephenson has particular interest in the response of materials to aggressive environments, analysis of mechanical behavior, and deformation and failure modes. He is adept in mechanical test techniques, experiment design, and a range of optical and electron microscopy techniques.

Dr. Stephenson completed his Ph.D. work at the University of Michigan in 2016, where his work focused on irradiation-assisted stress corrosion cracking of stainless steels used as structural components in nuclear reactor cores. During his dissertation project, Dr. Stephenson designed and developed a novel, miniaturized four-point bend experiment for testing highly irradiated stainless steels in a simulated reactor environment. The experiment allowed the observation of crack initiation sites at scales which had never before been achieved, and significantly improved understanding of the cracking process.

CREDENTIALS & PROFESSIONAL HONORS

  • Ph.D., Materials Science and Engineering, University of Michigan, Ann Arbor, 2016
  • M.S.E., Materials Science and Engineering, University of Michigan, Ann Arbor, 2012
  • B.S.E., Materials Science and Engineering, Washington State University, 2009

Publications

Stephenson KJ, Was GS. The role of dislocation channeling in IASCC initiation of neutron irradiated stainless steel. Journal of Nuclear Materials 2016; 481:214-225.

Stephenson KJ, Was GS.  Comparison of the microstructure, deformation and crack initiation behavior of austenitic stainless steel irradiated in-reactor or with protons.  Journal of Nuclear Materials 2015; 456:85-98.

Stephenson KJ, Was GS.  Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature water.  Journal of Nuclear Materials 2014; 444:1-3:331-341.

Malik H, Stephenson KJ, Bahr DF, Field DP.  Quantitative characterization of carbon nanotube turf topology by SEM analysis.  Journal of Materials Science 2011; 46:9:3119-3126.

Carroll MP, Stephenson K, Findley KO.  Characterization of high energy ion implantation into Ti–6Al–4V.  Journal of Nuclear Materials 2009; 389(2):48–253.

Conference Proceedings

Stephenson KJ, Was GS. Development of a novel SCC test for isolating crack initiation in neutron irradiated stainless steel. Proc. 17th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 2015.

Was GS, McMurtrey MM, Johnson D, Stephenson KJ, Robertson I, Farkas D, Smith L. Linkage between strain localization and environmentally assisted cracking. International Hydrogen Conference, Jackson, WY, 2016.

Gussev MN, Field KG, Busby JT, Stephenson KJ, Was GS. SEM-EBSD and TEM analysis of stress corrosion crack initiation sites in neutron-irradiated austenitic stainless steels. Proceedings, 17th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, 2015.

Stephenson KJ, Was GS. Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature water. In: Transactions of the American Nuclear Society 2014; 111:(1):139–142.

Stephenson KJ, Was GS. Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature water. In: Transactions of the American Nuclear Society 2013; 109(1):399–402.

Stephenson KJ, Was GS. Relationship between dislocation channeling and IASCC in neutron irradiated stainless steel. Proc.16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2013.

Was G, Stephenson K, Ashida Y. Insights into the IASCC mechanism in neutron irradiated austenitic alloys with varying microstructure and microchemistry. Proc.16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 2013.

Stephenson KJ, Ashida Y, Bsuby JT, Was GS. Stress corrosion crack initiation susceptibility of irradiated austenitic stainless steels. Proc. 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 2011; 1126–1138.

Presentations

Stephenson KJ, Was GS. New insights into IASCC initiation in neutron irradiated austenitic stainless steel. 17th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Ottawa, ON, 2015.

Gussev MN, Field KG, Bsuby JT, Stephenson KJ, Was GS. SEM-EBSD and TEM analysis of stress corrosion crack initiation sites in neutron-irradiated austenitic stainless steels. 17th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Ottawa, ON, 2015.

Stephenson KJ, Was GS. New insights into IASCC initiation in neutron irradiated austenitic stainless steel. ICG-EAC 2015, Ann Arbor, MI, 2015.

Stephenson KJ, Was GS. The role of localized deformation in IASCC initiation of neutron irradiated austenitic stainless steel. TMS 2015, Orlando, FL, 2015.

Stephenson KJ, Was GS. Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature water. ANS Winter Meeting, Anaheim, CA, 2014.

Stephenson KJ, Was GS. Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature water. Invited, ANS Winter Meeting, Washington D.C., 2013.

Stephenson KJ, Was GS. Relationship between dislocation channeling and IASCC in neutron irradiated stainless steel. 16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Asheville, NC, 2013.

Stephenson KJ, Ashida Y, Bsuby JT, Was GS. Stress corrosion crack initiation susceptibility of irradiated austenitic stainless steels. 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Colorado Springs, CO, 2011.

Stephenson KJ, Was GS. Uncovering the mechanisms of irradiation assisted stress corrosion cracking. American Nuclear Society Student Conference, Ann Arbor, MI, 2010.

Stephenson K, Findley K, Carroll M. Novel characterization methods for Ti-6Al-4V implanted with high energy ions. TMS Annual Meeting, New Orleans, LA, March 2008.

CREDENTIALS & PROFESSIONAL HONORS

  • Ph.D., Materials Science and Engineering, University of Michigan, Ann Arbor, 2016
  • M.S.E., Materials Science and Engineering, University of Michigan, Ann Arbor, 2012
  • B.S.E., Materials Science and Engineering, Washington State University, 2009