Curriculum Vitae
Zhijie (George) Jiao
Associate Research Scientist
Nuclear Engineering and Radiological Sciences
University of Michigan
1941 Cooley Building
2355 Bonisteel Boulevard, Ann Arbor, MI, 48109
Phone:734-615-7761 Fax:734-763-4540 Email: zjiao@umich.edu
Education
Ph.D. (2004), M.S. (2002) in Materials Science, Polytechnic University, New York
B.S.(1995), Metal Physics, M.E. (1998) in Materials Physics, U. of Sci. & Tech. Beijing
Employment
Department of Nuclear Engineering and Radiological Sciences, University of Michigan
Assoc. Res. Scientist
9/ 2012–
Asst. Res. Scientist
11/ 2007– 8/ 2012
Postdoc Res. Fellow, Sr. Res. Fellow
6/2004- 11/2007
Research Interests
Radiation effects on materials, materials degradation in the reactor environment, corrosion and
stress corrosion cracking, ion beam emulation of neutron damage, microstructural processes in
irradiated materials, microstructure characterization by transmission electron microscopy and
atom probe tomography.
Research Experience
•
•
•
•
•
•
•
•
•
•
•
Ion Beam Simulation of High Dose Neutron Irradiation
Mitigation Strategy for IASCC in Austenitic Stainless Steels
Irradiation-Accelerated Corrosion of Reactor Core Materials
Atom Probe Tomography in Understanding IASCC
Ion Irradiation-Induced Degradation of Reactor Structural Materials
Aging and Embrittlement of High Fluence Stainless Steels
Cladding and Structural Materials for Advanced Reactor Systems
Radiation-Induced Segregation and Phase Stability in Candidate Alloys for the Advanced
Burner Reactor
Irradiation Creep in Pyrolytic Carbon Used in TRISO Fuel Particles for VHTR
Mechanistic Basis for Irradiation-Assisted Stress Corrosion Cracking
Radiation effects, stress corrosion cracking and corrosion of candidate alloys (304SS,
316SS, Inconel 690, 625) for the Supercritical Water Reactor Concept
•
•
Radiation Effects in Candidate Materials for Spallation Neutron Environments
Deformation mechanism in TiAl
Honors and Activities
•
•
•
•
•
•
•
•
•
•
•
•
•
•
2011 Literary Award, Materials Science and Technology Division, American Nuclear
Society
2010 Innovations in Fuel Cycle Research Award (co-authored paper)
2009 Student Literary Award (best paper by student), Materials Science and Technology
Division (co-authored paper), American Nuclear Society
2008 Literary Award, Materials Science and Technology Division, American Nuclear
Society
Symposium co-organizer for “Microstructural Processes in Irradiated Materials”,
Orlando, FL. TMS2015
Symposium co-organizer for “Microstructural Processes in Irradiated Materials”, San
Antonio, TX. TMS2013
Guest editor, special issue of Journal of Nuclear Materials, Volume 449, Issues 1–3,
June 2014 for “Proceedings of the Symposium on Microstructural Processes in Irradiated
Materials (MPIM)”
Guest editor, special issue of Journal of Nuclear Materials, Volume 407, Issue 1, 1
December 2010 for “Proceedings of the Symposium on Microstructural Processes in
Irradiated Materials (MPIM) and on Reactor Pressure Vessel (RPV) Embrittlement and
Fusion Materials: Measuring, Modeling and Managing Irradiation Effects”
Invited reviewer for proposals submitted to the following DOE programs: Nuclear
Energy University Programs (NEUP), Basic Energy Sciences (BES), Small Business
Innovation Research (SBIR) program, and the Advanced Test Reactor National Scientific
User Facility (ATR NSUF)
Invited reviewer for manuscripts submitted to the following journals: Journal of Nuclear
Materials ; Corrosion Science ; Intermetallics , Journal of ASTM International ,
Engineering Failure Analysis , Materials Science and Engineering A, Acta Materilia ,
Journal of Material Research, etc
Executive Committee member , American Nuclear Society, Materials Science and
Technology Division , 2013SHaRE User Executive Committee member, Oak Ridge National Laboratory, 2009
Member of Nuclear Materials Committee, the National Scientific User Facility User’s
Group (NSUG), The Minerals, Metals & Materials Society (TMS) and the Microscopy
Society of America (MSA).
Broad collaborations with national laboratories and universities, EPRI, international
collaborators including INSS Japan, EDF France, etc.
Research grants
1. DOE-NE, IRP, High Fidelity Ion Beam Simulation of High Dose Neutron Irradiation, , PI.
Gary Was, Co-PI: Z. Jiao, P. Hosemann (UC Bekerly) B. Wirth (UT), A. Motta (Penn
State), D. Morgan (UW), D. Kaoumi (USC) and others, 03/01/2014 to 02/28/2017,
$4,764,125
2. TerraPower, Heavy Ion Irradiation of HT9, PI: Gary Was, Co-PI: Z. Jiao, 07/30/2014
to 08/31/2015, $ 322,872
3. Electric Power Research Institute (EPRI), Characterization of degree of localized
deformation using high resolution EBSD measurements, PI: Z. Jiao , 07/01/2012 to
12/31/2012, $20,000
4. DOE-NEUP, Accelerated Irradiations for High Dose Microstructures in Fast Reactor
Alloys, PI: Z. Jiao. Co-PI: Roger Stoller (ORNL), Stu Maloy (LANL), Emmanuelle
Marquis (UM), Gary Was (UM). September 2012-September 2015, $831,876
5. DOE-NEUP, Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing ,
PI: Gary Was (UM). Co-PI: Z. Jiao, Jeremy Busby (ORNL), September 2012-September
2015, $876,98
6. GE Global Research, Accident Tolerant Fuels for Light Water Reactors, PI: Gary Was
(UM). Co-PI: Z. Jiao, 01/01/2013 to 10/24/2014, $251,656
7. Electric Power Research Institute (EPRI), Mitigation Strategy for IASCC in Austenitic
Stainless Steels, PI: Z. Jiao, Co-PI: Gary Was and Emmanuelle Marquis (UM). April
2011 – September 2014, $402,962,
8. TerraPower, Heavy Ion Irradiation of HT9 Phase 1: Correlation of Neutron and Heavy
Ion Irradiation Behavior, PI: Gary Was, Co-PI: Z. Jiao, July 2011 – May 2014,
$964,739
9. Electricite De France (EDF), Irradiation-Accelerated Corrosion of Reactor Core
Materials (complimentary program), PI: Gary Was , Co-PI: Z. Jiao, April 2011–
October 2012, $20,000
10. Electric Power Research Institute (EPRI), Establishing a cause-and-effect relationship
between localized deformation and IASCC, PI: G. Was , Co-PI: Z. Jiao. August 2010 –
December 2013, $380,000
11. DOE-NEUP, Irradiation-Accelerated Corrosion of Reactor Core Materials, PI: Z. Jiao,
Co-PI: G. Was, David Bartels ( U. Notre Dame). September 2010 – August 2014.
$798,000
12. DOE-NEUP, Microstructure and Property Evolution in Advanced Cladding and Duct
Materials under Long-term and Elevated Temperature: Critical Experiments, PI: G. Was
, Co-PI: Z. Jiao, Todd Allen (U. of Wisconsin), Yong Yang (U. of Florida). September
2010 – August 2013, $1,181,377.
13. DOE-NNSA, Aging and Embrittlement of High Fluence Stainless Steels, PI: G. Was, CoPI: Z. Jiao, A. Van Der Ven (UM) and Dan Edwards (PNNL), October 2009 –
September 2012. $500,000
Publications
Journal articles
1. Z. Jiao; Gary Was; Terumitsu Miura; Koji Fukuya, Aspects of ion irradiations to study
localized deformation in austenitic stainless steels, Journal of Nuclear Materials
452(2014)328-334.
2. Z. Jiao; G.S. Was, Precipitate behavior in self-ion irradiated stainless steels at high doses,
Journal of Nuclear Materials 449(2014)200-206.
3. G.S. Was; Z. Jiao; E. Getto; K. Sun; A.M. Monterrosa; S.A. Maloy; O. Anderoglu; B.H.
Sencer; M. Hackett, Emulation of reactor irradiation damage using ion beams, Scripta
Materialia 88(2014)33.
4. S. Raiman; A. Flick; O. Toader; P.Wang; N. Samad; Z. Jiao; G.S. Was, A facility for
studying irradiation accelerated corrosion in high temperature water, Journal of Nuclear
Materials 451(2014)40-47.
5. F. Khatkhatay; L. Jiao; J. Jian; W. Zhang; Z. Jiao; J. Gan; H. Zhang; X. Zhang; H. Wang ,
Superior corrosion resistance properties of TiN-based coatings on Zircaloy tubes in
supercritical water, Journal of Nuclear Materials. 2014;451(1-3):346-351.
6. F. Wan, Q. Zhan, Y. Long, S. Yang, G. Zhang, Y. Du, Z. Jiao, S. Ohnuki, The behavior
of vacancy-type dislocation loops under electron irradiation in iron, Journal of Nuclear
Materials 455(2014)253-257
7. Y. Huang; J.P. Wharry; Z. Jiao; C.M. Parish; S. Ukai; T.R. Allen, Microstructural
evolution in proton irradiated NF616 at 773 K to 3 dpa, Journal of Nuclear
Materials 442(2013)800.
8. Z. Jiao and G.S. Was, Precipitate Evolution in Ion-Irradiated HCM12A, Journal of
Nuclear Materials 425(2012)105-111
9. J.P. Wharry, Z. Jiao, G.S. Was, Application of the inverse Kirkendall model of radiationinduced segregation to ferritic–martensitic alloys, Journal of Nuclear Materials 425
(2012) 117-124
10. E. West, M. McMurtrey, Z. Jiao, G.S. Was, Role of Localized Deformation in IASCC
Initiation, Metallurgical and Materials Transactions A 43(2012)136-146
11. Z. Jiao, V. Shankar, and G.S. Was, Phase Stability in Proton and Heavy Ion Irradiated
Ferritic-Martensitic Alloys, Journal of Nuclear Materials 419 (2011) 52.
12. Z. Jiao, M. McMurtrey, G.S. Was, Strain-Induced Precipitate Dissolution in an Irradiated
Austenitic Alloy, Scripta Materialia 65 (2011) 159-163.
13. Z. Jiao and G.S. Was, Segregation Behavior in Proton- and Heavy Ion-Irradiated FerriticMartensitic Alloys, Acta Materialia 59 (2011) 4467-4481
14. Z. Jiao and G.S. Was, Novel Features of Radiation-Induced Segregation and RadiationInduced Precipitation in Austenitic Stainless Steels, Acta Materialia 59 (2011) 1220-1238.
15. J. Wharry, Z. Jiao, V. Shankar and G.S. Was, Radiation-induced Segregation and Phase
Stability in Ferritic-Martensitic Alloy T-91, Journal of Nuclear Materials 417 (2011) 140.
16. Y.N. Huang, F.R. Wan and Z. Jiao, The Type Identification of Dislocation Loops by
TEM and the Loop Formation in Pure Fe Implanted with H+, Acta Physics Sinica 60
(2011) 036802.
17. Z. Jiao and G.S. Was, Impact of Localized Deformation on Irradiation-Assisted Stress
Corrosion Cracking of Austenitic Stainless Steels, Journal of Nuclear Materials 408
(2011) 246.
18. Z. Jiao and G.S. Was, The Role of Irradiation Microstructure in Localized Deformation in
Austenitic Alloys, Journal of Nuclear Materials 407 (2010) 34-43.
19. R. Zhou, E.A. West, Z. Jiao and G.S. Was, Irradiation-Assisted Stress Corrosion
Cracking of Austenitic Alloys in Supercritical Water, Journal of Nuclear Materials 395
(2009) 11-22.
20. Z. Jiao and G.S. Was, Localized Deformation and IASCC Initiation in Austenitic
Stainless Steels, Journal of Nuclear Materials 382 (2008) 203.
21. Z. Jiao, A.N. Ham, and G.S. Was, Microstructure of Helium-implanted and Protonirradiated T91 Ferritic/Martensitic Steel, Journal of Nuclear Materials 367-370 (2007)
440-445.
22. S. Teysseyre, Z. Jiao, E. West, G.S. Was, Effect of Irradiation on Stress Corrosion
Cracking In Supercritical Water, Journal of Nuclear Materials 371 (2007) 107-117.
23. Z. Jiao, J.T. Busby and G.S. Was, Deformation Microstructure of Proton-irradiated
Stainless Steels, Journal of Nuclear Materials 361 (2007) 218-227.
24. G.S. Was, S. Teysseyre, and Z. Jiao, Corrosion of Austenitic Alloys in Supercritical
Water, Corrosion 62 (2006) 989-1005.
25. G. Gupta, Z. Jiao, G.S. Was, A.N. Ham, J.T. Busby, Microstructural Evolution of Proton
Irradiated T91, Journal of Nuclear Materials 351 (2006)162-173.
26. Z. Jiao, S.H. Whang and Q. Feng, Stability of ordinary dislocations on cross-slip planes
in γ-TiAl, Materials Science and Engineering A 329-332 (2002) 171-176.
27. Z. Jiao, S.H. Whang and Z. Wang, Stability and cross-slip of [101] superdislocations in γTiAl, Intermetallics 9 (2001) 891-898.
28. M.C. Iordache, S.H. Whang, Z. Jiao and Z.M. Wang, Grain growth kinetics study in
nanostructured nickel, Nanostructured Materials, 11 (1999) 1343-1349.
Conference proceedings
1. Z. Jiao, Y. Chen, E. Marquis, G.S. Was, Post-Irradiation Annealing in Mitigation of
IASCC of Proton-Irradiated Stainless Steel, 16th International Conference on
Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors,
Asheville, NC., 2013
2. Elizabeth Beckett; Micah Hackett; Z. Jiao; Kai Sun; Gary S. Was , Microstructural
evolution of self-ion irradiated HT9, International Conference on Nuclear Engineering,
Proceedings, ICONE. 2013;1.
3. Z. Jiao and G.S. Was, Oxidation of a Proton-irradiated 316 Stainless Steel in Simulated
BWR NWC Environment, Proc. 15th Int. Conf. on Environmental Degradation of
Materials in Nuclear Power Systems– Water Reactors, 2011, pp.1329-1338.
4. W. Lai, Z. Jiao, G.S. Was, Effect of Environment and Prestrain on IASCC of Austenitic
Stainless Steels. Proc. 15th Int. Conf. on Environmental Degradation of Materials in
Nuclear Power Systems– Water Reactors, 2011, pp.1397-1412.
5. Z. Jiao, V. Shankar, J. Wharry and G.S. Was, Phase Stability in Proton and Heavy Ion
Irradiated Ferritic-Martensitic Alloys, Transactions of the American Nuclear Society. Vol.
102, pp. 824. 0-17 Jun 2010.
6. S. Choudhury, L. Barnard, D. Morgan, K. Field, T. Allen, J. Wharry, Z. Jiao, G.S. Was,
B. Wirth, Radiation Induced Segregation in Ferritic-Martensitic Steels, Transactions of
the American Nuclear Society. Vol. 102, pp. 715. 0-17 Jun 2010.
7. Z. Jiao and G.S. Was, Atom Probe Tomography of Radiation-induced Precipitation in
Reactor Cladding and Structural Steels, Microscopy and Microanalysis, Volume 16,
Supplement S2, July 2010, pp. 1598.
8. Z. Jiao J. Penisten G. Was and R. Martens, Atom Probe Tomography of RadiationInduced Precipitation in Ferritic-Martensitic Alloy HCM12A, Microscopy and
Microanalysis, Volume 15, Supplement S2, July 2009, pp. 1374.
9. Z. Jiao, G.S. Was and P. Chou, Atom Probe Tomography Study of IASCC of ProtonIrradiated Austenitic Stainless Steels, Proc. 14th Int. Conf. on Environmental Degradation
of Materials in Nuclear Power Systems, American Nuclear Society, Lagrange Park, IL,
2009, pp.1240-1247.
10. E. West, Z. Jiao and G.S. Was, Influence of Taylor Factor on IASCC in SCW and
Simulated BWR Environments, Proc. 14th Int. Conf. on Environmental Degradation of
Materials in Nuclear Power Systems, American Nuclear Society, Lagrange Park, IL,
2009, pp.1690-1701.
11. G.S. Was, R. Zhou, E.A. West and Z. Jiao, Irradiation Assisted Stress Corrosion Cracking
of Austenitic Alloys in Supercritical Water, Proc. 14th Int. Conf. on Environmental
Degradation of Materials in Nuclear Power Systems, American Nuclear Society,
Lagrange Park, IL, 2009, pp.1679-1689.
12. G.S. Was, Z. Jiao and J. T. Busby, Recent Developments in Understanding the
Mechanism of IASCC, Research for Aging Management of Light Water Reactors and its
Future Trend, Brain L. Eyre and Itsuro Kimura (Eds.), Institute of Nuclear Safety System,
Inc., Fukui, Japan, 2008, pp. 157-180.
13. Z. Jiao, G.S. Was and J.B. Busby, The Role of Localized Deformation in IASCC of
Proton-irradiated Austenitic Stainless Steels, Proc. 13th Int’l Conf. Environmental
Degradation of Materials in Nuclear Power Systems – Water Reactors, (2007). Paper No:
P0051.
14. 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, Proc. 13th Int’l Conf. Environmental Degradation of Materials in
Nuclear Power Systems – Water Reactors, (2007), Paper No: P0062
15. G.S. Was, Z. Jiao and J.T. Busby, Contribution of Localized Deformation to
IGSCC/IASCC in Austenitic Stainless Steels, Proc. the 16th European Conference of
Fracture (ECF 16), Alexandroupolis, Greece, July 2006, Paper No: 509.
16. G.S. Was, S. Teysseyre, J. McKinley, Z. Jiao, Corrosion of Austenitic Alloys in
Supercritical Water, NACE's Annual Conference, Corrosion 2005, Paper No: 05397,
(2005).
17. 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,
Proc. 12th Int’l Conf. Environmental Degradation of Materials in Nuclear Power
Systems – Water Reactors, Salt Lake City, UT., (2005). pp.379-388.
Industrial reports
1. Potential for Atom Probe Tomography in Understanding IASCC. EPRI, Palo Alto,
CA:2011. EP-P25947/C12545
2. Program on Technology Innovation: A Mechanistic Basis for Irradiation-Assisted Stress
Corrosion Cracking. EPRI, Palo Alto, CA: 2009. 1019031
3. The Use of Proton Irradiation to Determine IASCC Mechanisms in Light Water Reactors
– Phase 3: Deformation Studies. EPRI, Palo Alto, CA: 2006. 1013081.
Invited talks
1. Emulation of Neutron Irradiated Microstructures with Ion Irradiation, Project X Energy
Station Workshop, Fermi National Accelerator Laboratory, January 29-30, 2013
2. Microstructure and Property Evolution in Advanced Cladding and Duct: Materials under
Long-Term and Elevated Temperature, ANS 2012, Chicago, IL. June 26, 2012
3. High Dose Microstructures in Ferritic-Martensitic Alloys, School of Energy Research,
Xiamen University, May 3, 2012
4. Strategies for Studying Irradiation Effects in Materials using Ions, National Center for
Materials Safety, U. of Sci. & Tech. Beijing, April 25, 2012
5. High Dose Microstructures in Ferritic-Martensitic Alloys, Materials and Fuels for the
Current and Advanced Nuclear Reactors, TMS2012, Orlando, FL. March 11-15, 2012
6. Role of High Ni and High Cr Content in IASCC of Austenitic Alloys, Alloy 800 COG
(CANDU Owners Group Inc. )Meeting, Toronto, November 19-20, 2012
7. Novel Features of the Irradiated Microstructure in Austenitic Stainless Steels and FerriticMartensitic Steels using Atom Probe Tomography, Idaho National Laboratory, June 10,
2011
8. Atom Probe Tomography of Radiation-induced Precipitation in Reactor Cladding and
Structural Steels, Microscopy and Microanalysis 2010, Portland, OR, August 1-5 2010.