Researcher

James Cole

Directorate Fellow, Nuclear Science and Technology

Research Areas:

Biography:

Dr. James Cole has more than 24 years of increasing leadership experience conducting and managing research and development of nuclear fuels and reactor structural materials for nuclear energy systems. Dr. Cole's efforts have emphasized relating the fundamental radiation-induced changes in structure and chemistry to life-limiting ageing and performance degradation. Areas of expertise include nuclear fuel development and qualification, irradiation testing, post-irradiation examination, advanced cladding development, development of radiation tolerant materials for next generation reactors and study of radiation damage effects on reactor structural materials. In addition, Dr. Cole played a key leadership role in specifying and procuring multiple state-of-the-art characterization tools for Idaho National Laboratory leading to pioneering irradiated nuclear fuel characterization advances.

During Dr. Cole's Tenure as chief scientist of the Department of Energy Office of Nucelar Energy (DOE-NE) Nuclear Sciences User Facilities (formerly the Advanced Test Reactor NSUF), the program established several new initiatives (e.g., irradiated materials and fuels library, rapid turnaround experiments) while bringing in additional partner facilities and supporting impactful university and industry led research efforts. As the current U.S. High Performance Research Reactor Fuel Qualification (USHPRR FQ) pillar national technical lead, Dr. Cole provides technical and professional leadership to a team of more than 50 INL staff focused on qualifying high-density low-enriched uranium fuels to enable conversion of high-performance research reactors and meet US government nonproliferation objectives.

Dr. Cole has contributed to 55 peer reviewed journal publications, 30 peer reviewed conference papers and two book chapters. Dr Cole has also mentored a total of 13 graduate, undergraduate and high school students and two post-doctoral researcher over his career. Dr. Cole's university collaborations have led to five Ph.D.'s and five M.S.'s. As an adjunct or affiliate faculty member, Dr. Cole has served on graduate committees of four students.

Education:

Ph.D., Materials Science - Washington State University

M.S., Materials Science and Engineering - Washington State University

B.S., Materials Science and Engineering - Washington State University

Training

Basic/Lead Auditor NQA-1 Orientation Training (2021)

Idaho National Laboratory “License to Lead" (2013)

ANT International Training Course on “Zirconium Based Alloys for Nuclear Systems" (2011)

ANT International Training Course on “UO₂ and MOX Fuel Performance" (2012)

Affiliations:

The Minerals, Metals and Materials Society (TMS)

American Nucelar Society (ANS)

Materials Research Society

Publications:

Book Chapters

James I Cole, Jan-Fong Jue, Glenn A Moore, “Fuel design and fabrication: Research reactor fuel", In: Greenspan, E. (Ed.), Encyclopedia of Nuclear Energy, vol. 2. Elsevier, pp. 326–333.

James I Cole, Hakan Ozaltun, Jan-Fong Jue, Warren F Jones, Dennis D Keiser Jr , Barry Rabin, and Mitchell K Meyer,, “Irradiation Performance: Research Reactor Fuels", In: Greenspan, E. (Ed.), Encyclopedia of Nuclear Energy, vol. 2. Elsevier, pp. 420–428.

Refereed Journal Publications

T.R. Pavlov, S.C. Middlemas, B.D. Miller, F. Cappia, J.I. Cole, J.J. Giglio, “Understanding the local thermal conductivity evolution of neutron irradiated U₃Si₂ dispersion fuel via state-of-the-art thermo-reflectance measurements", Journal of Nuclear Materials Volume 557, 15 December 2021, 153280.

F. G. Di Limmea, J. Burns, J. W. Madden, A. J. Winston, A. B. Robinson, J. F. Jue, D. D. Keiser, J. I. Cole, “Texture Analyses and Microstructural Evolution in Monolithic U-Mo Nuclear Fuel", Journal of Nuclear Materials, November 2020, 152677.

Jason M. Harp, Luca Capriotti*, Douglas L. Porter, James I. Cole “U-10Zr and U-5Fs: Fuel/Cladding Chemical Interaction Behavior Differences", Journal of Nuclear Materials 528 (2020) 151840.

Silva Kalcheva, Geert Van den Branden, Steven Van Dyck, Sven Van den Berghe, Greg K. Housley, Nicolas E. Woolstenhulme, Irina Glagolenko, James I. Cole, “Feasibility studies for simultaneous irradiation of NBSR & MITR fuel elements in the BR2 reactor" Annals of Nuclear Energy 127 (2019) 303–318.

R. Newell, A. Mehta, Y.J. Park, D.D. Keiser Jr., J.I. Cole, Y.H. Sohn, Microstructural characteristics of plasma sprayed, electroplated, and co-rolled Zr diffusion barriers in hot isostatic pressed low enriched U-10 wt% Mo monolithic fuel plates, Journal of Nuclear Materials 523 (2019) 91e100.

Jerred, N. D., Charit, I., Zirker, L. R., & Cole, J. I. “Pressure resistance welding of MA-957 to HT-9 for advanced reactor applications", Journal of Nuclear Materials, 508 (2018. 265–277. https://doi.org/10.1016/j.jnucmat.2018.05.046.

Abhishek Mehta1, Le Zhou1, A. Schulz1, Dennis D. Keiser Jr., J. I. Cole, Sohn J., “Microstructural Characterization of AA6061 Versus AA6061 HIP Bonded Cladding–Cladding Interface", J. Phase Equilib. Diffus. 39 (2018) 246–254.

C.M. Barr, P.J. Felfer, J.I. Cole, M.L. Taheri, “Observation of oscillatory radiation induced segregation profiles at grain boundaries in neutron irradiated 316 stainless steel using atom probe tomography", Journal of Nuclear Materials 504 (2018) 181-190.

Somayeh Pasebani, Indrajit Charit, Ankan Guria, Yaqiao Wu, Jatuporn Burns, Darryl P. Butt, J. I. Cole, Lin Shao, “A preliminary investigation of high dose ion irradiation response of a lanthana-bearing nanostructured ferritic steel processed via spark plasma sintering", Journal of Nuclear Materials, 495 (2017) 78-84.

Somayeh Pasebani, Indrajit Charit, Yaqiao Wu, Jatuporn Burns, Kerry N. Allahar, Darryl P. Butt, J. I. Cole, and Sultan F. Alsagabi , “Lanthana-bearing nanostructured ferritic steels via spark plasma sintering", Journal of Nuclear Materials 470 (2016) 297-306.

Assel Aitkaliyeva, James W. Madden, Brandon D. Miller, Cynthia A. Papesch, J. I. Cole, “TEM Examination Of Phases Formed Between U-Pu-Zr Fuel And Fe", Journal Of Nuclear Materials 467 (2015) 717-723.

Somayeh Pasebani, Indrajit Charit,* Darryl P. Butt, J. I. Cole, Yaqiao Wu and Jatuporn Burns, “Sintering Behavior Of Lanthana-Bearing Nanostructured Ferritic Steel Consolidated Via Spark Plasma Sintering", Advanced Engineering Materials (2015), Doi: 10.1002/Adem.201500294.

Assel Aitkaliyeva, James W. Madden, Brandon D. Miller, Cynthia A. Papesch, and J. I. Cole, “Fuel-Cladding Interaction Between U-Pu-Zr Fuel And Fe", Metallurgical And Materials Transactions E, Volume 2E (2015) 220-228.

Somayeh Pasebani, Indrajit Charit, Jatuporn Burns, Sultan Alsagabi, Darryl P. Butt , J. I. Cole, Lloyd M. Price, Lin Shao, “Microstructural stability of a self-ion irradiated lanthana-bearing nanostructured ferritic steel", Journal of Nuclear Materials 462 (2015) 191–204.

Assel Aitkaliyeva, James W. Madden, Brandon D. Miller, J. I. Cole, Jian Gan, “Comparison of preparation techniques for nuclear materials for transmission electron microscopy (TEM)", Journal of Nuclear Materials 459 (2015) 241–246.

Colin D. Judge. Nicolas Gauquelin, Lori Walters, Mike Wright, J. I. Cole, James Madden, Gianluigi A. Botton, Malcolm Griffiths, “Intergranular fracture in irradiated Inconel X-750 containing very high concentrations of helium and hydrogen", Journal of Nuclear Materials 457 (2015) 165–172.

Ahmad Alsabbagh, Apu Sarkar, Brandon Miller, Jatuporn Burn, Leah Squires, Douglas Porter, J. I. Cole, K.L. Murty “Microstructure and mechanical behavior of neutron irradiated ultrafine grained ferritic steel" Materials Science & Engineering A 615 (2014)128–138

Peter B. Wells, Takuya Yamamoto, Brandon Miller, Tim Milot, J.I. Cole, Yuan Wua, G. Robert Odette “Evolution of manganese–nickel–silicon-dominated phases in highly irradiated reactor pressure vessel steels" Acta Materialia 80 (2014) 205–219.

A. Aitkaliyeva, J.W. Madden, B.D. Miller, J.I. Cole, Implementation of focused ion beam (FIB) system in characterization of nuclear fuels and materials" Micron 67 (2014) 65–73

Y. Q. Wu, K. N. Allahar; J. Burns; B. Jaques; I. Charit, D. P. Butt and J. I. Cole^,“Characterization of ODS alloys by SPS - A combinational TEM and APT study" Cryst. Res. Technol. 49, No. 9, (2014) 645–652.

Kerry N. Allahar, Jatuporn Burns, Brian Jaques, Yaqiao Wu, Indrajit Charit, J. Cole, Darryl P Butt, “Ferritic Oxide Dispersion Strengthened Alloys by Spark Plasma Sintering", Journal of Nuclear Materials 443 (2013) 256–265.

S. Pasebani, I. Charit, Y.Q. Wu, D.P. Butt, J.I. Cole “Mechanical alloying of lanthana-bearing nanostructured ferritic steels", Acta Materialia, v 61, n 15 (2013) 5605-5617.

Fauzia Khatkhatay, Jie Jian, Liang Jiao, Qing Su, Jian Gan, J. I. Cole, Haiyan Wang, “Diffusion barrier properties of nitride-based coatings on fuel cladding", Journal of Alloys and Compounds, v 580 (2013) 442-448.

I. Kim, L. Jiao, F. Khatkhatay, M.S. Martin, J. Lee, L. Shao, X. Zhang, J.G. Swadener, Y.Q. Wang, J. Gan , J. Cole, H. Wang, “Size-dependent radiation tolerance in ion irradiated TiN/AlN nanolayer films", Journal of Nuclear Materials, v 441, n 1-3 (2013) 47-53.

Somayeh Pasebani, Indrajit Charit, Darryl P. Butt, J. I. Cole, “A preliminary study on the development of La₂O₃-bearing nanostructured ferritic steels via high energy ball milling", Journal of Nuclear Materials, v 434, n 1-3 (2013) 282-286.

Rita Kirchhofer, John D. Hunn, Paul A. Demkowicz, J. I. Cole, Brian P. Gorman, “Microstructure of TRISO coated particles from the AGR-1 experiment: SiC grain size and grain boundary character", Journal of Nuclear Materials 432 (2013) 127–134.

Ickchan Kim , Fauzia Khatkhatay , Liang Jiao, Greg Swadener, J. I. Cole, Jian Gan, Haiyan Wang, “TiN-based coatings on fuel cladding tubes for advanced nuclear reactors", Journal of Nuclear Materials 429 (2012) 143–148.

Vahid Firouzdor, Lucas Wilson, Kumar Sridharan, Brandon Semerau, Benjamin Hauch, Jamieson Brechtl, J. I. Cole, Todd R. Allen ,“Development of Diffusion Barrier Coatings for Mitigation of Fuel-Cladding Chemical Interactions", Key Engineering Materials, Electrophoretic Deposition: Fundamentals and Applications IV, v 507 (2012) 3-7.

S.A. Maloy, M. Toloczko, J. Cole, T.S. Byun, “Core Materials Development for the Fuel Cycle R & D Program", Journal of Nuclear Materials 415(2011) 302–305.

B.H. Sencer, J.R. Kennedy, J.I. Cole, S.A. Maloy, F.A. Garner “Microstructural stability of an HT-9 fuel assembly duct irradiated in FFTF", Journal of Nuclear Materials 414 (2011) 237–242.

B. H. Sencer, J. R. Kennedy, J. I. Cole, S. A. Maloy, F. A. Garner, Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155 dpa at 443°C, Journal of Nuclear Materials, v 393, n 2 (2009) 235-241.

Frary, M., Schlegel, S., Hopkins, S., Young, E., Cole, J., Lillo, T., “Analysis of Precipitate Redistribution in Inconel 617 Using Integrated Electron Backscatter Diffraction and Energy Dispersive Spectroscopy", Microscopy and microanalysis, vol:15 (2009) 24 -25.

S. Schlegel, S. Hopkins, E. Young, J. Cole, T. Lillo, and M. Frary, “Precipitate Redistribution during Creep of Alloy 617", Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science, v 40, n 12 (2009) 2812-2823.

T. Lillo, J. Cole, M. Frary, and Scott Schlegel “Influence of Grain Boundary Character on Creep Void Formation in Alloy 617", Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science, v 40, n 12 (2009) 2803-2811.

T. R. Allen, J. Gan, J. I. Cole, M. K. Miller, J. T. Busby, S. Shutthanan and S. Thevuthasan, “Radiation Response of a 9 Chromium Oxide Dispersion Strengthened Steel to Heavy-Ion Irradiation", Journal of Nuclear Materials 375 (2008) 26–37.

T.R. Allen, J.I. Cole, E.A. Kenik, and G.S. Was, “Analyzing the Effect of Displacement Rate on Radiation-Induced Segregation in 304 and 316 stainless Steels by Examining Irradiated EBR-II Components and Samples Irradiated with Protons", J. of Nucl. Mat. 376 (2008) 169–173.

T. R. Allen, K. Sridharan, L. Tan, W. E. Windes, J. I. Cole, and D. C. Crawford, G.S. Was, “Materials Challenges for Generation IV Nuclear Energy Systems", Nucl. Tech. 162 (2008) 342-357.

J. Gan, J. I. Cole, T. R. Allen and S. Shutthanandan, S. Thevuthasan, "Irradiated Microstructure of Alloy 800H," J. Nucl. Mater. 351(1-3) (2006) 223-227.

J. I. Cole, H. Tsai, T. R. Allen, T. Yoshitake, N. Akasaka, I. Yamagata, and Y. Nakamura,,"Strain-Rate Effects on Microstructural Deformation in Irradiated 316 SS", J. Nucl. Mater. 351(1-3) (2006) 316-323.

T. R. Allen, J. I. Cole, C. L. Trybus, D. L. Porter, H. Tsai, F. Garner, E. A. Kenik, T. Yoshitake, Joji Ohta, “The effect of dose rate on the response of austenitic stainless steels to neutron radiation", J. Nucl. Mater. 348 (2006) 148.

J. I. Cole, T. R. Allen, H. Tsai, T. Yoshitake, I. Yamagata, N. Akasaka and Y. Nakamura, “Low Strain-Rate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBR-II" Journal of ASTM International, February 2006, Vol. 3. No. 2,DJAI12400.

T. Yoshitake, I. Yamagata, N. Akasaka, Y. Nakamura, H. Tsai, J. I. Cole and T. R. Allen, “Behavior of Irradiated Type 316 Stainless Steels under Low-Strain-Rate Tensile Conditions", Journal of ASTM International (JAI), JAI12346.

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, v. 342 (2005) 90-100.

T. R. Allen, J. Gan, J. I. Cole, S. Ukai, S. Shutthanandan and S., Thevuthasan, “The Stability of 9Cr-ODS Oxide Particles under Heavy Ion Irradiation", Nuclear Science and Engineering, v. 151, n. 3 (2005) 305-312.

D. D. Keiser, Jr. and J. I. Cole, “Fuel-Cladding Compatibility in Metallic Nuclear Fuels," TMS Letters, vol. 2 No. 3 (2005) 79-80.

Gan, J, Cole, J. I., Allen, T. R., Dropek, R. B., Was, G. S. “Effect of Zr on the irradiated microstructure and hardening in 304 stainless steel", Fusion Science and Technology, Volume 44, Issue 1 (2003) 191-195.

J. I. Cole and T. R. Allen, "Microstructural Changes Induced by Post-Irradiation Annealing of Neutron-irradiated Austenitic Stainless Steels", J. Nucl. Mater., 283-287 (2000) 329.

T. R. Allen, J. I. Cole, C. L. Trybus, and D. L. Porter, "The Effects of Long Time Irradiation and Thermal Aging on 304 Stainless Steel," J. Nucl. Mater. 282 (2000) 171.

T. R. Allen, J. I. Cole, E. A. Kenik, H. Tsai, S. Mizuta, T. Yoshitake, “Using Fast Reactor Component Evaluation for Pressurized Water Reactor Life Extension", JOM-Journal of the Minerals Metals & Materials Society, 51 (10), (1999) 27-30.

T. R. Allen, C. L. Trybus and J. I. Cole, "The Effects of Low Dose-Rate Irradiation and Thermal Aging on Reactor Structural Alloys", J. Nucl. Mater, 270 (1999) 290-300.

S. G. Song, J. I. Cole and S. M. Bruemmer, "Formation of Partial Dislocations During Intersection of Glide Dislocations with Frank Loops in FCC Lattices", Acta Materialia, 45(2) (1997) 501.

J. I. Cole, and S. M. Bruemmer, "Post-Irradiation Deformation Characteristics of Heavy-ion Irradiated 304L SS", J. Nucl. Mater., 225 (1995) 53.

S. M. Bruemmer, B. W. Arey, J. I. Cole and C. F. Windisch, "Irradiation Effects on the Electrochemistry and Corrosion Resistance of Stainless Steel", Corrosion J., 51 (1995) 11.

J. L. Brimhall, J. I. Cole and S. M. Bruemmer, "Deformation Microstructures in Ion-Irradiated Stainless Steel", Scripta Met. 30 (1994) 1473.

J. I. Cole, D. S. Gelles and J. J. Hoyt, "Phase Stability of Reduced-activation Mn-stabilized Austenitic Steels", J. Nucl. Mater. 191-194 (1992) 657.

Conference Proceedings – Full Papers

E. H. Wilson, C. Lavender, M. Cercy, J. I. Cole and K. Dunn, “Preliminary Fuel Development and Reactor Design Milestones for LEU Conversion of U.S. High Performance Research Reactors," Proc. Int. Conf. Nuclear Security, Vienna, Austria, January 10–14, 2020, International Atomic Energy Agency (2020).

C.D. Judge, H. Rajakumar, A. Korinek, G. Botton, J. Cole, J.W. Madden, J.H. Jackson, P.D. Freyer, L.A. Giannuzzi, C. Parish and M. Griffiths, “High Resolution Transmission Electron Microscopy of Irradiation Damage in Ex-service Inconel X-750", Proceedings of 18^th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, pp 727-741.

J. I. Cole, Barry H. Rabin, James A. Smith, Clark L. Scott, Bradley C. Benefiel, Eric D. Larsen, Paul R. Lind, and David A. Sell, “U.S. Progress On Property Characterization To Support LEU U-10 Mo Monolithic Fuel Development", RRFM 2016, European Research Reactor Conference, European Nuclear Society Paper A0215.

R. D. Mariani, J. I. Cole, A. Aitkaliyeva “Novel Zr-1Nb Alloy And a New Look at Hydriding," 2013 LWR Fuel Performance Meeting/ TopFuel 2013, American Nuclear Society, Charlotte, NC, September 15-19, 2013, pp. 986-994.

R. D. Mariani, P. Medvedev, D. L. Porter, S. L. Hayes, J. I. Cole, X-M. Bai “Novel Accident-Tolerant Fuel Meat and Cladding," 2013 LWR Fuel Performance Meeting / TopFuel 2013, American Nuclear Society, Charlotte, NC, September 15-19, 2013, pp. 763-771.

N. Jerred, L. Zirker, B. Jaques, T. Bradshaw, J. Carrillo, E. Young, I. Charit, J. Cole, M. Frary, D.P. Butt, M. Meyer, and K.L. Murty “Pressure Resistance Welding of High Temperature Metallic Materials," Proceedings of Joining of Advanced and Specialty Materials XII, Materials Science and Technology 2010, Houston, TX, Oct. 17-21, 2010.

D. D. Keiser and J. I. Cole, “An Assessment of Layer Development at the Fuel/Cladding Interface During Irradiation of Metallic SFR Fuel Elements", Materials Research Society Symposium Proceedings, Volume: 1125 (2009) Pages: 73-79.

R. Prabhakaran, D. E. Burkes, D. M. Wachs, J. I. Cole and I.Charit, “Small-Scale Specimen Testing of Monolithic UMo Fuel Foils" Proceedings of RERTR 2008 - 30th INTERNATIONAL MEETING ON REDUCED ENRICHMENT FOR RESEARCH AND TEST REACTORS proceedings.

D. D. Keiser, Jr. and J. I. Cole, “An Evaluation of Potential Liner Materials for Eliminating FCCI in Irradiated Metallic Nuclear Fuel Elements", GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems, (2007) p 597-604,.

J. I. Cole, D. D. Keiser and J. R. Kennedy, “Microstructural Characterization of Cast Metallic Transmutation Fuels", GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems, (2007) p 1375-1379.

J. Rempe, D. Knudson, K. Condie, and J. I. Cole, “Long Duration Performance of High Temperature Irradiation Resistant Thermocouples", Proceedings of ICAPP 2007, Paper 7371.

J. I. Cole, T. R. Allen, G. S. Was Dropek, R. B., and Kenik, E. A., “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, ASTM STP 1447, M. L. Grossbeck, T. R. Allen, R. G. Lott, and A. S. Kumar, Eds., Ed., (ASTM International, West Conshohocken, PA, 2004) p. 540.

T. R. Allen, H. Tsai, J. I. Cole, J. Ohta, K. Dohi, H. Kusanagi,., “Properties of 20% Cold-Worked 316 Stainless Steel Irradiated at Low Dose Rate," Effects of Radiation on Materials, ASTM STP 1447, (ASTM International, West Conshohocken, PA, 2004) p. 3.

J. Gan, T. Allen, J. I. Cole, S. Ukai, S. Shutthanandan and S. Thevuthasan, “The Irradiated Microstructure of Ferritic-Martensitic Steel T91 and 9Cr-ODS", Proceedings of MRS Full meeting, Boston, 2003, Radiation Effects and Ion-Beam Processing of Materials, Editors: Lu-Min Wang, Rainer Fromknecht, Lance L. Snead, Daniel F. Downey, Heishichiro Takahashi, Vol. 792, Paper No. R1.7

J. I. Cole, T. R. Allen, J. Gan, G. S. Was, R. B. Dropek and E. A. Kenik, “Development of Radiation-Tolerant Austenitic Stainless Steels for Advanced Reactor Applications", Proceeding of ANS Global 2003, New Orleans, L.A. Nov. 16-20, 2003, CD-ROM, American Nuclear Society, pp 1812.

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", 11th Int. Conf. Environmental Degradation of Materials in Nuclear Systems, Stevenson, WA, Aug. 10-14, 2003, p. 1132.

T.Yoshitake, T.Donomae, S.Mizuta, H.Tsai, Robert V. Strain, T.R.Allen, and J.I.Cole, "Tensile Properties of 12% Cold-Worked 316 Stainless Steel Irradiated at EBR-II Reactor with Lower Dose Rate Conditions to High Fluence," Effects of Radiation on Materials: 20th International Symposium, ASTM STP 1405, S. T. Rosinski, M. L. Grossbeck, T. R. Allen, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA 2002, p. 469.

J. I. Cole, T. R. Allen, H. Tsai, S. Ukai, S. Mizuta and T. Yoshitake, "Swelling and Microstructural Evolution in 316 Stainless Steel Hexagonal Ducts Following Long-Term Irradiation in EBR-II", Effects of Radiation on Materials: 20th International Symposium, ASTM STP 1405, S. T. Rosinski, M. L. Grossbeck, T. R. Allen, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA 2002, p. 413.

T. R. Allen, J. I. Cole, and E. A. Kenik, "Radiation-Induced Segregation and Void Swelling in 304 Stainless Steel," Effects of Radiation on Materials: 20th International Symposium, ASTM STP 1405, S. T. Rosinski, M. L. Grossbeck, T. R. Allen, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2002, p.427.

J. I. Cole, T. R. Allen, G. S. Was, Y. Wang, and E. A. Kenik, “The Effect of Bulk Composition on the Radiation-Induced Microstructures and Segregation Behavior in Model Austenitic Stainless Steel Alloys: A Proton Irradiation Study", Proceedings of the Tenth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, National Association of Corrosion Engineers, August 5-9, 2001, Lake Tahoe, Nev, CD-Rom.

T. R. Allen, H. Tsai, J. I. Cole, J. Ohta, K. Dohi, and H. Kusanagi , "Mechanical Properties of 20% Cold-Worked 316 Stainless Steel Irradiated at Low Dose Rate," Proceedings of the 10th International Conference on Nuclear Engineering, American Society of Mechanical Engineering, paper 10-22189.

T. R. Allen and J. I. Cole, H. Tsai, T. Yoshitake, T. Donamae, N. Akasaka, Mechanical properties and microstructural development in irradiated 316 stainless steel, 16th International Conference on Structural Materials in Reactor Technology (SmiRT-16) Washington, DC August 12-17, 2001, Paper G11/6.

J. I. Cole, T. R. Allen, H. Kusanagi, K. Dohi, and J. Ohta, "Microstructure and Post-Irradiation Annealing Behavior of 20% Cold-Worked 316 Stainless Steel", in Microstructure Processes in Irradiated Materials. Mat. Res. Soc. Symp. Proc. Vol. 650, Materials Research Society (2001) R2.9.

T. R. Allen, J. I. Cole, J. Ohta, H. Kusanagi, and E. A. Kenik, "Radiation-Induced Segregation in 316 and 304 Stainless Steel Irradiated at Low Dose Rate," in Microstructure Processes in Irradiated Materials. Mat. Res. Soc. Symp. Proc. Vol. 650, Materials Research Society (2001) R2.4.

T. R. Allen , J. I. Cole, N. L. Dietz, Y. Wang, G. S. Was, and E. A. Kenik, "The Effect of Bulk Composition on Swelling and Radiation-induced Segregation in Austenitic Alloys," in Microstructure Processes in Irradiated Materials. Mat. Res. Soc. Symp. Proc. Vol. 650, Materials Research Society (2001) R3.12.

T. R. Allen, J. I. Cole, H. Tsai, S. Ukai, S. Mizuta, and T. Yoshitake, The Effect of Low Dose Rate Irradiation on the Swelling of 12% Cold-Worked 316 Stainless Steel, Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, , S. Bruemmer, P. Ford, G,. Was Eds., Newport Beach, CA, TMS, Warrendale, PA, (August 1999), p.1035.

T. R. Allen and J. I. Cole, and E. A. Kenik, “The Effect of Low Dose Rate Irradiation on the Grain Boundary Chemistry in 304 Stainless Steel", Mat. Res. Soc. Symp. Proc. Vol. 540, Materials Research Society (1999) 507.

S. M. Bruemmer, J. I. Cole, R. D. Carter, G. S. Was, "Defect Microstructures and Deformation Mechanisms in Irradiated Austenitic Stainless Steels", MRS Symposium Proceedings: Microstructure Evolution During Irradiation, (Materials Research Society, 1996) 437.

J. I. Cole, J. L. Brimhall, J. S. Vetrano, and S. M. Bruemmer, "Deformation Temperature, Strain Rate and Irradiation Microstructure Effects on Localized Plasticity in 304L SS", Proceedings of the 7th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (NACE, 1995) 817.

S. M. Bruemmer, T. F. Soran, J. I. Cole, B. W. Arey, L. A. Charlot and C. F. Windisch, Jr., "Radiation-Induced Segregation of Impurities and Effects on the Electrochemistry of Nickel and Stainless Alloys", published as part of Corrosion 95, National Association of Corrosion Engineers, paper 95420 (1994).

S. M. Bruemmer, J. I. Cole, J. L. Brimhall, R. D. Carter and G. S. Was, "Radiation Hardening Effects on Localized Deformation and Stress Corrosion Cracking of Stainless Steels", 6th International symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (TMS, 1993) 277.

Presentations:

Invited Talks

ANS Annual Meeting, “Monolithic U-10Mo Fuel Development for U.S. High Performance Research Reactors", 2016, New Orleans, LA.

ANS Winter Meeting “Fuels and Materials Characterization Capabilities at the Idaho National Laboratory and the Center for Advanced Energy Studies", 2015, Washington, DC.

The Ohio State University Invited Seminar, “Conducting Nuclear Science and Technology Research through the ATR National Scientific User Facility" 2014, Columbus, OH.

University of Florida Graduate Seminar, Conducting Nuclear Science and Technology Research through the ATR National Scientific User Facility, 2014, Gainesville, FL.

International Conference on Processing & Manufacturing of Advanced Materials: Thermec 2013, “Application of Solid-State Joining Techniques to Dispersion Strengthened Alloys Intended for Advanced Nuclear Energy Systems", 2013, Las Vegas, NV.

Society of Mining Engineers Uranium Symposium, “Nuclear Power Plant Material Selection- What makes it happen", Feb. 2007, Denver, CO.

Refereed Extended Abstracts Associated with Conference Presentations

J. I. Cole, B. Rabin,, I. Glagolenko, N. Woolstenhulme, A. Robinson, D. Keiser, H. Ozaltun, W. Williams, F. Rice, G. Moore, J. Gan, J. Smith, M. Meyer, D. Wachs, G. Hofman, Y. Kim, “Monolithic U-10Mo Fuel Development for U.S. High Performance Research Reactors" Transactions 2016 ANS Annual Meeting, New Orleans, Louisianna.

A. Aitkaliyeva, J. W. Madden, B. D. Miller, J. I. Cole, J. Gan, “Sample preparation artifacts in nuclear materials and mitigation strategies", Microscopy and Microanalysis 21(S3):999-1000, August 2015, DOI: 10.1017/S1431927615005796.

Maloy, S. A., Hosemann, P., Vanden Bosch, J. Toloczko, M. Cole, J., Byun, T. S. “Development and testing of radiation tolerant clad materials for nuclear fuels" Transactions of the American Nuclear Society, Volume 102, 2010, Page 701.

J. I. Cole, Assel Aitkaliyeva, James W. Madden and Brandon D. Miller, “The Focused Ion Beam-SEM as a Critical Tool For Nano-scale Characterization of Highly Radioactive Nuclear Fuels" Microscopy and Microanalysis 2014 Proceedings pg 1808-1809.

Allen, T. R., Benson, J. B., Cole, J. I., Knight, C. J., Marshall, F. M., Thelen, M. C., “The Advanced Test reactor National Scientific User Facility", Transactions of the American Nuclear Society, Volume 106, 2012, Pages 588-589.

Mohammadian, M., Sridharan, K., Allen, T., Cole, J., Fielding, R., “Characterization of vanadium-lined fuel cladding with various fabrication parameters", Transactions of the American Nuclear Society, Volume 102, 2010, Pages 808-809.

Prabhakaran, R., burkes, D., Robinson, A., Jue, J.–F., Demint, A., Gooch, J., Keiser, D., Wachs, D., Cole, J., Charit, I, “An investigation of the mechanical properties of fresh and irradiated U-Mo fuel", Transactions of the American Nuclear Society, Volume 102, 2010, Pages 806-807.

Prabhakaran, R., Wang, J. Yuan, W. Chitrada, K., Cole, J., Charit, I., Mishra, R., “Friction stir welding of oxide dispersion strengthened alloys", Transactions of the American Nuclear Society, Volume 102, 2010, Pages 857-858.

J. I. Cole , T. P. O'Holleran, D. D. Keiser Jr., and J. R. Kennedy “Out-of-pile effects of lanthanide rare-earth elements on fuel-cladding compatibility", Transactions of the American Nuclear Society and Embedded Topical Meeting Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NFSM, v 102, (2010) p 882-883.

M. A. Mohammadian, T. R. Allen, K. Sridharan, J. I. Cole, R. F. Fielding, C. Young, “Characterization of Vanadium-lined Fuel Cladding Fabricated with Various Process Parameters", Transactions of the American Nuclear Society and Embedded Topical Meeting Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, v 102, , (2010) p 808-809.

J. I. Cole and R. F. Fielding, “Cladding Liner Development for GNEP Transmutation Fuels" Transactions of the American Nuclear Society, v 99, (2008) p 307-308.

R. Prabhakaran, J. I. Cole, D. E. Burkes, J. Gan and I. Charit, “Small-scale Specimen Testing of Monolithic Fuels and Structural Materials", ANS Transactions Vol. 98, 2008 Spring Meeting, Anaheim, California, Nuclear Fuels and Structural Materials Symposium, June 8-12 (2008) pp. 1049-1050.

J. I. Cole, J. R. Kennedy and D. D. Keiser, “An Investigation of Fuel Cladding Chemical Interaction in Metallic Transmutation Fuels", ANS Transactions Vol. 98, 2008 Spring Meeting, Anaheim, California, Nuclear Fuels and Structural Materials Symposium, June 8-12 (2008) pp. 1109-1110.

T. R. Allen, J. Gan, J. I. Cole, S. Ukai, S. Shutthanandan and S. Thevuthasan, "Radiation Response of a 9 Cr Oxide Dispersion Strengthened ODS to Heavy Ion Irradiation," Transactions of the 2006 ANS Annual Meeting, Reno, NV, Vol. 94, June 2006, p. 829-830.

D. D. Keiser and J. I. Cole, "Chemical Interactions Between Metallic SFR Fuel and Advanced Claddings" Transactions of the 2006 ANS Annual Meeting, Reno, NV, Vol. 94, June 2006, p. 775-776.

J. I. Cole, C. R. Clark and J. F. Jue., "Use of Friction Stir Welding and Friction Stir Processing for Advanced Nuclear Fuels and Materials Joining Applications", Transactions of the 2006 ANS Annual Meeting, Reno, NV, Vol. 94, June 2006, p. 654-655.

R. S. Daum, J. I. Cole, D. L. Porter, T. R. Allen, H. Tsai, and B. D. Wirth, “Plastic Flow And Fracture Of Cold-Worked 316 Stainless Steel", Proceedings of 2002 American Nuclear Society Winter Meeting.

T. R. Allen, J. I. Cole, N.L. Dietz, Y. Wang, G. S. Was, and E. A. Kenik, "The Effect of Bulk Composition on Microstructural Changes in Austenitic Alloys," Transactions of the 2000 ANS Winter Meeting, American Nuclear Society, LaGrange Park, IL, p. 205.

T. R. Allen and J. I. Cole, "Stress Relaxation in Irradiated Inconel X750 Springs," 1999 ANS Annual Meeting Proceedings.

J. I. Cole, D. O'Brien, M. Qian and R. M. Fisher, "Characterization of Adhesive-Primer Penetration Into Porous Oxides Formed on Anodized Aluminum Using Electron Energy Loss Spectroscopy" Proceedings: Microscopy and Microanalysis '97, (Microscopy Society of America, 1997) 777.

Awards:

ANS MSTD 2015 Literary Award, Paper Entitled “Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at 295 _C to 6.5 dpa", S.A. Maloy, T.A. Saleh, O. Anderoglu, T.J. Romero, G.R. Odette, T. Yamamoto, S. Li, J.I. Cole, R. Fielding, Journal of Nuclear Materials (2015) 1-8.

Center for Advanced Energy Studies Outstanding Contributor Award 2013.

INL Exceptional Contribution/Recognition Awards (~8 times)

JAEA Certificate and Medallion of Recognition for supporting JAEA/ANL collaboration.

Associated Western Universities, Laboratory Graduate Fellowship (PNNL) (1990-1996)

2^nd place, Los Angeles Chapter of ASM International Metallography Contest (1992).

Member of Alpha Sigma Mu (Materials Science Honor Society) (1989).

Recipient of Kaiser Aluminum and Chemical Company Scholarship (1988).

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