James Stubbins

Profile Photo
Willett Professor and Department Head
(217) 333-2295
jstubbinatillinois [dot] edu
216 Talbot Laboratory
MC 234
104 S. Wright Street
Urbana, IL 61801
 
Degrees
  • Ph.D., Materials Science, University of Cincinnati, 1975
  • M.S., Nuclear Engineering, University of Cincinnati, 1972
  • B.S., Nuclear Engineering, University of Michigan, 1970
Academic Positions
  • Donald Biggar Willett Professorship - January 2013 - December 2017
  • Department Head – January 1999 – present
  • Adjunct Professor, Chemical Engineering, The Ohio University, 1991 - 1998
  • Associate Head - November, 1991 – December 1998
  • Professor - Fall 1991 - present
  • Faculty Appointee, Division of Educational Programs, Argonne National Laboratory, 1989 - 2000
  • Faculty Appointee, Northwest College and University Association for Science (NORCUS), Battelle Pacific Northwest Laboratory, Richland, WA, June 1987-2000
  • Associate Professor - Fall 1985 - Summer 1991
Research Topics
  • Advanced Energy Systems and Energy Policy

  • Nuclear materials, irradiation damage and effects, mechanical properties, high temperature corrosion, and electron microscopy.

  • Nuclear systems design and analysis.

  • Development, analysis and application of materials, primarily for energy-related applications.

Consulting Activities
  • Oak Ridge National Laboratory
  • The Ohio State University
  • Argonne National Laboratory
  • International Atomic Energy Agency
  • Battelle's Pacific Northwest Laboratory
  • Los Alamos National Laboratory
  • Department of Energy
Research Topics
  • Advanced Energy Systems and Energy Policy

  • Nuclear materials, irradiation damage and effects, mechanical properties, high temperature corrosion, and electron microscopy.

  • Nuclear systems design and analysis.

  • Development, analysis and application of materials, primarily for energy-related applications.

Publications
Book Chapters
  • Rawlins, C.B., J. Tanaka, D.J. Barta, C.A. Harper, J.F. Stubbins, D.E. Lyon. "Properties of Materials," Standard Handbook for Electrical Engineers, D.G. Fink, H.W. Beatty, Eds. Fourteenth Edition, McGraw-Hill, (1999).
  • *Shong, W-J., J.F. Stubbins, J.G. Williams, JW. Rogers,and M. Giacobbe, "Neutron dosimetry and mechanical properties changes monitoring by magnetic response of Fe and Ni wires," Reactor Dosimetry, Eighth Symposium, ASTM STP 1228, H. Farrar IV, E.P. Lippincott, and J.G. Williams, Eds. ASTM, 1228, 215-224 (1994).
  • *Stubbins, J.F., W.-J., Shong, M. Giacobbe, A.M. Ougouag, and J.G. Williams, "Pressure vessel steel embrittlement monitoring by magnetic properties measurements," Small Specimen Test Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension, ASTM STP 1204, W.R. Corwin, F.M. Haggag, and W.L. Server, Eds., American Society for Testing and Materials, Philadelphia, 5-15, (1993).
  • *Hour, K-Y., and J.F. Stubbins, "Effect of mean loading on creep and fatigue crack growth at elevated temperature," 24th National Symposium on Fracture Mechanics, ASTM-Special Technical Publication 1207 (1993).
  • *Ougouag, A.M., M.B. Danjaji, J.G. Williams, J.F. Stubbins, and M. A. Ghaly, "Defect production efficiency in neutron-irradiated iron," Effects of Radiation on Materials: 15th International Symposium, ASTM STP 1125, R. E. Stoller, A. S. Kumar, and D. S. Gelles, Eds., American Society for Testing and Materials, Philadelphia, 420-433, (1992).
  • *Anderson, K.R., F.A. Garner, and J.F. Stubbins, "Mechanical property changes and microstructures of dispersion-strengthened copper alloys after neutron irradiation at 411, 414 and 529° C ," 15th Int'l. Symp. on the Effects of Radiation on Materials, R. Stoller, A. Kumar and D. Gelles, Eds., ASTM STP (1992).
  • *Anderson, K.R., F.A. Garner, and J.F. Stubbins, "Unusual tensile and fracture behavior of pure copper at high levels of neutron-induced swelling," 15th Int'l. Symp. on the Effects of Radiation on Materials, R. Stoller, A. Kumar and D. Gelles, Eds., ASTM STP (1992).
  • *Hour, K-Y, and J.F. Stubbins, "Crack growth behavior in three heat resistant materials at elevated temperature," Fracture Mechanics; 22nd Symp. , H. A. Ernst, A. Saxena, and D. L. McDowell, Eds., ASTM STP, 1131 Vol. 1, 318-341 (1992).
  • *Stubbins, J.F., J.E. Nevling, F.A. Garner, and R.L. Simons, "Microstructural evolution of neutron-irradiated Fe-Cu-Ni alloys at 495o C in response to charges in He/DPA ratio," Effects of Irradiation on Materials, ASTM STP, 104 Vol. 1, 147-159 (1990).
  • *Stubbins, J.F., A.M. Ougouag, and J.G. Williams, "The effects of mechanical stress gradients on irradiation induced embrittlement of pressure vessel steels," ASTM STP, 1046 Vol. 2, 305-322 (1990).
  • *Stubbins, J.F. "Phase stability in Fe-15Ni-XCr alloys under ion or electron irradiation,” Effects of Radiation on Materials, ASTM-STP, 956, 758-774 (1987).
  • *Holloway, J.P. and J.F. Stubbins, "Phase stability in irradiated alloys by constrained equilibrium thermodynamics" in Effects of Radiation on Materials, Twelfth Int. Symp., ed. F. A. Garner and J. S. Perrin, ASTM-Special Tech. Publ. 870, 167-183 (1985).
Conference Articles
  • Stubbins, J.F., Bolind, A.M. and Chen, X., “The electrical impedance response of steel surface oxide layers in molten lead—bismuth eutectic,” Spallation Materials Technology, Proceedings of the Eighth International Workshop on Spallation Materials Technology, (2008)
  • Srivilliputhur, S.G., Deo, C.S., Okuniewski, M., Baskes, M.I., James, M.R., Maloy, S.A., and Stubbins, J.F., “Multiscale Modeling of Radiation Damage in Reactor Materials,” American Nuclear Society Winter Meeting, Washington, D.C., (2005).
  • Deo, C., Blas , P., Uberuaga, B.P., Srivilliputhur, S.G., Maloy, S.A., Patten, T., and Stubbins, J.F., “Multiscale Simulations of Defects in Hyperstoichiometric Uranium Di-Oxide,” MMSNF-4, American Nuclear Society Winter Meeting, Washington, D.C., (2005).
  • Wu, X., Pan, X., Li, M., Stubbins, J.F., “Flow Localization Modeling for Face-Centered Cubic (FCC) Metals After Exposure to Radiation,” American Nuclear Society, American Nuclear Society Winter Meeting, Washington, D.C., (Nov. 2004)
  • Wu, X., Pan, X., Li, M., Stubbins, J.F., “Flow Localization Processes in Austenitic Alloys,” 22 International Symposium on the Effects of Radiation on Materials, Boston, MA (Jun. 2004)
  • Li, M. and Stubbins, J.F., “Creep-Fatigue Behavior in High Strength Copper Alloys,” Proceedings of the 22nd International Symposium on the Effects of Radiation on Materials, Boston, MA (Jun 2004).
  • Li, Meimei and Stubbins, James F., “Fatigue Response and Life Prediction of Selected Reactor Materials,” Effects of Radiation on Materials: 21st International Symposium, Tucson, AZ (2002)
Journal Articles
  • Tung, H.-M., Mo, K. and J.F. Stubbins, "Biaxial thermal creep of Inconel 617 and Haynes 230 at 850 and 950oC," Journal of Nuclear Materials, V. 447, Issue 1-3, pp 28-37, (April 2014)

  • Chen, X., Yang, Z., Sokolv, M. A., Erdman III, Donald I., Mo, K. and J. F. Stubbins, "Effect of creep and oxidation on reduced fatigue life of Ni-based alloy 617 at 850 oC.", Journal of Nuclear Materials, v 444, pp 393-403 (2014)

  • Tulenko, J. S., Beyer, C. E., Yang, Y., Fuchs, G. E., Stubbins, J., and K. B. Eapen, "Low Temperature Creep of Used Nuclear Fuel During Long Term Dry Storage," International High-Level Radioactive Waste Management, articles in press (2013).

  • Chen, X and J. F. Stubbins, "Low Cycle Fatigue and Creep-Fatigue Behavior of Ni-based Alloy 230 at 850 degrees C", Materials Science and Engineering A,v 563, pp 152-162 (Feb. 2013).

  • Chen, X., Sokolov, Mikhail A., Sham, S., Erdman III, D.L., Busby, J. T., Mo., K. and J. F. Stubbins, "Experimental and modeling results of creep-fatigue life of inconel 617 and Haynes 230 at 850 degrees C," Journal of Nuclear Materials, v 432 (1-3), pp 94-101 (Jan 2013).

  • Ye, B., Oaks, A., Kirk, M., Yun, D., Chen, W-Y., Holtzman, B. and J.F. Stubbins, "Irradiation Effects in UO2 and CeO2," Journal of Nuclear Materials, v. 441, Issue 1-3, pp. 525-529 (2013)

  • Tung, H.-M. and J. F. Stubbins, "Incipient corrosion behavior of Haynes 230 under a controlled reducing atmosphere at high temperatures," Journal of Nuclear Materials, 427 (1-3), pp. 389-392 (2012).

  • Tung, H-M. and J. F. Stubbins, "Incipient oxidation kinetics of alloy 617 and residual stress of the oxide scale formed in air at temperatures between 850 and 1000C," Journal of Nuclear Materials, 424 (1-3), pp. 23-28, (2012).

  • Tung,H-M. and J. F. Stubbins, "Incipient oxidation kinetics and residual stress of the oxide scale grown on Haynes 230 at high temperatures," Materials Science and Engineering A, v 538, pp 1-6 (2012).

  • Ye, B., Yun, D., Oaks, A. J., Chen, W., Kirk, M. A., Rest, J., Yacout, A.M. and J.F. Stubbins, "Fission gas transport and its interactions with irradiation-induced defects in lanthanum doped ceria," Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms,v 272, pp 239-243 (2012).

  • Ye, B. Yun, D., Oaks, A. J., Chen, W., Kirk, M. A., Rest, J., Yacout, A.M. and J.F. Stubbins, "The effects of xenon implantation in ceria with and without lanthanum," Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, v 272, pp 236-238 (2012)

  • Chen, X., Haasch,R., and J. F. Stubbins, "Impedance spectroscopy and microstructural characterization of the corrosion behavior of FeCrAl alloy in lead-bismuth eutectic," Journal of Nuclear Materials, v 431(1-3), pp 125-132 (Dec. 2012).

  • Yun, D., Oaks, A.J., Chen, W.-Y., Kirk, MA., Rest, J., Insopov, ZZ, Yacout, A.M., Stubbins, J.F., "Erratum: Kr and Xe irradiations in lanthanum (La) doped ceria: Study at the high dose regime," Journal of Nuclear Materials, v 418(1-3) (80-86) (2011).

  • Ye, B., Kirk, M.A., Chen, W., Oaks, A., Rest, J., Yacout, A., Stubbins, J.F., "TEM investigation of irradiation damage in single crystal CeO2," Journal of Nuclear Materials, 414(2), pp 251-256 (2011).

  • Oaks, A., Yun, D., Ye, B., Chen, W-Y and J. F. Stubbins, "Kinetic Monte Carlo model of defect transport and irradiation effects in La-doped CeO2," Journal of Nuclear Materials, 414(2), pp 145-149 (2011).

  • Mo, K., Lovicu, G., Tung, H.-M., Chen, X. and J. F. Stubbins, "High temperature aging and corrosion study on alloy 617 and alloy 230," Journal of Engineering for Gas Turbines and Power, 133 (5), art. no. 052908(9 pp)(2011)

  • Kun Mo, Gianfranco Lovicu, Hsiao-Ming Tung, Xiang Chen, James F. Stubbins, "Microstructural Evolution of Alloy 617 and Alloy 230 following High Temperature Aging", Proceedings of the ASME, Pressure Vessels & Piping Division, PVP2010-25847 (2010).

  • Kun Mo, Xiang Chen, Gianfranco Lovicu, Hsiao-Ming Tung, James F. Stubbins, "Mechanism of Plastic Deformation of a Ni-based Superalloy for VHTR Applications", Transactions of the American Nuclear Society, v 102, pp 850-851 (2010).

  • Ye, B., Yun, D., Kirk, M., Oaks, A., Chen, W.Y., Holztman, B., ElBakhshwan, M. and J.F. Stubbins, "Irradiation effects in UO2 and CeO2," Transactions of the American Nuclear Society, v 102, pp 765-766 (2010).

  • Pan, X., Wu, X., Mo, K., Chen, X., Almer, J., Ilavsky, J., Haeffner, D.R. and J. F. Stubbins, "Lattice strain and damage evolution of 9-12%Cr ferritic/martensitic steel during in situ tensile test by X-ray diffraction and small angle scattering," J. Nucl. Mater., 407(1) 10-15 (2010).

  • Mo, K., Lovicu, G., Tung, H.-M., Chen, X. and J. F. Stubbins, "In-plane anisotropy in microstructure and mechanical behavior of Alloy 617 following high temperature aging," TMS 2010. 139th Annual Meeting & Exhibition. Supplemental Proceedings, Volume 2: Materials Characterization, Computation, Modeling and Energy, 491-8 (2010).

  • Wu, X., Pan, X. and James F. Stubbins, "Notch Strengthening and Its Impact on the Deformation and Fracture of 316L Stainless Steel," ASTM Special Technical Publication, 1492, Effects of Radiation on Materials: 23rd Internatl. Symposium, 134-148 (Nov. 2008).

  • Wu, Xianglin, Pan, X. and Stubbins, J. F., "Notch strengthening and its impact on the deformation and fracture of 316L stainless steel," Journal of ASTM International, v 5, n 6 (Jun. 2008).

  • Pan, X., Wu, X., Fu, G. and Stubbins, J. F., “Grain size effect on room temperature fatigue and creep-fatigue behavior of OFHC cooper,” Fusion Science and Technology, 52:3, 521-5, (Oct. 2007).

  • Wu, X., Pan, X., Mabon, J. C., Li, M., and Stubbins, J. F., “An EBSD investigation on flow localization and microstructure evolution of 316L stainless steel for Gen IV reactor applications,” J. Nucl. Mater, 371, 1-3, 90-7 (15 Sep. 2007).

Reports
  • Bolind, A., Chen, X. and J. F. Stubbins, "Real Time Corrosion Monitoring in Lead and Lead-Bismuth Systems, (Final Report)", Department of Energy, Washington, DC., DOE/ID/14667, 35p (Feb 2010).
Professional Societies
  • American Society of Engineering Education - Member, 1999 - present
  • Nuclear Engineering Department Heads Organization (NEDHO) - Member 1999 - present
  • ANS - Chair, Honors and Awards, Materials Science and Technology Division, 1998 - present
  • ANS - Executive Committee, Materials Science and Technology Division 1996- present
  • American Nuclear Society (ANS) - Fellow, 2007 - present
  • American Nuclear Society - Member 1987 - present
Professional Registrations
  • Professional Engineer, State of Illinois (062-040835)
Other Honors
  • Donald Biggar Willett Professor

  • Outstanding Achievement Award, Materials Science and Technology Division

  • Media Relations Award -
    Award for Communications & Marketing Excellence 2011

  • Engineering Council Award for Excellence in Advising

  • Glenn Murphy Award

  • Fellow

  • International Scientist of the Year

  • American Men and Women of Science

  • Who's Who in Technology Today

  • Alpha Sigma Mu

  • Tau Beta Pi - Eminent Engineer

  • Alpha Nu Sigma