Profile Picture

Lingfeng He

Distinguished Staff Scientist and High-Resolution Materials Characterization (HRMC) Group Lead

Research Areas:
Advanced Characterization; Materials Science and Engineering; Materials Properties and Performance


Lingfeng He is a distinguished scientist and HRMC group leader in Advanced Characterization Department at Idaho National Laboratory. Dr. He received his PhD degree in materials science at Chinese Academy of Sciences in China in 2009, and then worked as postdoctoral research associate and assistant scientist at Nagaoka University of Technology, Japan, and the University of Wisconsin-Madison before joined INL in 2014.  Dr. He is interested in materials behavior under extreme environments, with a focus on environmental degradation of materials in nuclear power systems. Dr. He's goal is to understand how the processing and radiation/corrosion environments change the microstructure of materials and its effects on the mechanical, corrosion and thermal properties of materials. He probed these interactions by virtue of cutting-edge electron microscopy and spatially resolved spectroscopy techniques. His current research projects include microstructure characterization of as-fabricated and irradiated nuclear fuels (oxide fuels, nitride fuels, silicide fuels, and metallic fuels) as well as advanced structural materials (ceramics, steels and nickel based alloys). Dr.  He services as the PI/Co-PI for Basic Energy Sciences (BES) Core Program, Energy Frontier Research Centers (EFRCs), International Nuclear Energy Research Initiative (I-NERI) project, Laboratory Directed Research and Development (LDRD) projects, Nuclear Energy University Program (NEUP) project, Nuclear Science User Facility (NSUF) Rapid Turnaround Experiments (RTEs) and SBIR/STTR. Dr. He has authored/co-authored 105 peer-reviewed journal publications, with an H-index of 26, cited over 1700 times (Web of Science), 145 technical presentations (including 34 invited) and held 5 patents. He is a reviewer of 44 journals, e.g. Acta Materialia, Corrosion Science, Journal of the American Ceramic Society, Journal of Nuclear Materials, PNAS. He is also an active reviewer for proposals from US Department of Energy (DOE), Office of Nuclear Energy, NEUP, NSUF, DOE Office of Science, SBIR/STTR, LDRD at Idaho National Laboratory. He has been a mentor for 5 postdoctoral researchers, 3 graduate students and 6 summer intern students.​

Digital Profiles:

B. Eng. in Metallurgical Science and Engineering, Central South University, China, 2003

Ph.D. in Materials Science, Chinese Academy of Sciences (CAS), China, 2009​



The Minerals, Metals & Materials Society

The American Ceramic Society


  1. C.A. Dennett, W.R. Deskins, M. Khafizov, Z. Hua, A. Khanolkar, K. Bawane, L. Fu, J.M. Mann, C.A. Marianetti, L. He, D.H. Hurley, A. El-Azab, An Integrated Experimental and Computational Investigation of Defect and Microstructural Effects on Thermal Transport in Thorium Dioxide, Acta Mater. 213 (2021) 116934.
  2. A. Khanolkar, T. Yao, Z. Hua, C.A. Dennett, S.J. Reese, R.S. Schley, L. He, J.R. Kennedy, D.H. Hurley: In-situ Monitoring of Microstructure Evolution during Thermal Processing of Uranium-Zirconium Alloys using Laser-Generated Ultrasound, J. Nucl. Mater. 553 (2021) 153005.
  3. K. Bawane, X. Liu, T. Yao, M. Khafizov, A. French, J.M. Mann, L. Shao, J. Gan, D. Hurley, L. He: TEM Characterization of Dislocation Loops in Proton Irradiated Single Crystal ThO2, J. Nucl. Mater. 552 (2021) 152998.
  4. Z. Xiao, L. He, and X.-M. Bai: First Principles Studies of Effects of Solute Segregation on Grain Boundary Strength in Ni-Based Alloys, J. Alloys Compd. 874 (2021) 159795.
  5. T. Yao, A. Sen, A. Wagner, F. Teng, M. Bachhav, A. El-Azab, D. Murray, J. Gan, D.H. Hurley, J.P. Wharry, M.T. Benson, and L. He: Understanding Spinodal and Binodal Phase Transformations in U-50Zr Alloy, Materialia, 16 (2021) 101092.
  6. Y. Sun, T. Wu, Y. Bao, Y. Li, D. Wan, K. Li, L. He: Preparation and Strengthening Mechanism of Pre-Stressed Ceramic Tile Components, Int. J. Appl. Ceram. Tech. (2021) in press.
  7. R. Yuan, J. Zhang, L. He, J.-M. Zuo: Training Artificial Neutral Networks for Precision Orientation and Strain Mapping using 4D Electron Diffraction Datasets, Ultramicroscopy, (2021) in press.
  8. F.G. Di Lemma, C.B. Jensen, J.J. Kane, W.-Y. Chen, X. Liu, L. Carpriotti, C.A. Adkins, B. Kombaiah, A.J. Winston, L. He, and D. Wachs, Metallic Fast Reactor Separate Effect Studies for Fuel Safety, J. Nucl. Eng. Rad. Sci. 7 (2021) 041602.
  9. L. He, M. Khafizov, C. Jiang, B. Tyburska-Püschel, B. Jaques, P. Xiu, P. Xu, M. Meyer, K. Sridharan, D. Butt, and J. Gan: Phase and Defect Evolution in Uranium-Nitrogen-Oxygen System under Irradiation, Acta Mater. 208 (2021) 116778.
  10. K. Bawane, P. Manganaris, Y. Wang, J. Sure, A. Ronne, P. Halstenberg, S. Dai, S. K. Gill, K. Sasaki, Y. K. Chen-Wiegart, R. Gakhar, S. Mahurin, S. M. Pimblott, J. F. Wishart, L. He: Determining Oxidation States of Transition Metals in Molten Salt Corrosion using Electron Energy Loss Spectroscopy, Scripta Mater., 197 (2021) 113790.
  11. V.S. Chauhan, J. Pakarinen, T. Yao, L. He, D. Hurley and M. Khafizov: Indirect Characterization of Point Defects in Proton Irradiated Ceria, Materialia 5 (2021) 101019.
  12. S. K. Gill, J. Sure, Y. Wang, B. Lane, L. He, S. Mahurind, J. F. Wishart, and K. Sasaki: Investigating Corrosion Behavior of Ni and Ni-20Cr in Molten ZnCl2 Salt, Corro. Sci. 179 (2021) 109105.
  13. X. Liu, L. Capriotti, T. Yao, J.M. Harp, M.T. Benson, Y. Wang, and L. He: Fuel-Cladding Chemical Interaction of a Prototype Annular U-10wt.%Zr Fuel with HT-9 Cladding, J. Nucl. Mater. 544 (2021) 152588.
  14. C.A. Dennett, Z. Hua, A. Khanolkar, T. Yao, P.K. Morgan, T.A. Prusnick, N. Poudel, A. French, K. Gofryk, L. He, L. Shao, M. Khafizov, J.M. Mann, D.H. Hurley, The Influence of Lattice Defects, Recombination, and Clustering on Thermal Transport in Single Crystal Thorium Dioxide, APL Mater. 8 (2020) 111103.
  15. T. Yao, L. Capriotti, X. Liu, Y. Wang, J. Harp, J. Gan, M. Benson, and L. He: α-U and ⍵-UZr2 in Neutron Irradiated U-10Zr Annular Metallic Fuel, J. Nucl. Mater. 542 (2020) 152536.
  16. C. Parkin, M. Moorehead, M. Elbakhshwan, W.-Y. Chen, J. Hu, M. Li, L. He, K. Sridharan, A. Couet: In Situ Microstructural Evolution in FCC and BCC Complex Concentrated Solid-Solution Alloys under Heavy Ion Irradiation, Acta Mater. 198 (2020) 85-99.
  17. S.K. Gill, M. Topsakal, E. Jossou, X. Huang, K. Hattar, J. Mausz, M. Elbakhshwan, H. Yan, Y.S. Chu, C. Sun, L. He, J. Gan, L. Ecker: Impact of Krypton Irradiation on a Single Crystal Tungsten: Multi-modal X-ray Imaging Study, Scr. Mater. 188 (2020) 296-301.
  18. A. Hoffman, M. Arivu, H. Wen, L. He, K. Sridharan, X. Wang, W. Xiong, X. Liu, L. He, Y. Wu: Enhancing Resistance to Irradiation Induced Ferritic Transformation in Nanostructured Austenitic Steels, Materialia, 13 (2020) 100806.
  19. Z. Yu, T. Kim, M. Bachhav, X. Liu, L. He, A. Couet: Effect of Proton Pre-irradiation on Corrosion of Zr-0.5Nb Model Alloy with Different Nb Distribution, Corr. Sci. 173 (2020) 108790.
  20. T. Chen, L. He, M. Cullison, C. Hay, J. Burns, Y. Wu, L. Tan: The Correlation between Microstructure and Nanoindentation Property of Neutron-Irradiated Advanced Stainless Steel D9, Acta Mater. 195 (2020) 1-13.
  21. S. Johns, L. He, K. Bustillo, W.E. Windes, R. Ubic, C. Karthik: Fullerence-Like Defects in High-Temperature Neutron-Irradiated Nuclear Graphite, Carbon, 166 (2020) 113-122. 
  22. Y. Wang, T. Yao, F. Xi, P. Lei, X. Guo, L. He, G. Frankel, J. Lian: Degradation Mechanisms of Lead-Vanado-iodoapatite in Liquid-mediated NaCl Solutions, Corr. Sci. 172 (2020) 108720.
  23. Y. Zhang, Y. Lin, L. He, M. Vijayakumar, M.S. Bhuvaneswari, G. Pawar, B.M. Sivakumar, H. Ding, D. Ding, B. Liaw, E.J. Dufek, Bin Li: Dual Functional Ni3S2@Ni Core-shell Nanoparticles Decorating Nanoporous Carbon as Cathode Scaffolds for Lithium-Sulfur Battery with Lean Electrolytes, ACS App. Energy Mater. 3 (2020) 4173-4179.
  24. M. Khafizov, M. F. Riyad, Y. Wang, J. Pakarinen, L. He, T. Yao, A. El-Azab, D. Hurley: Combining Mesoscale Thermal Transport and X-ray Diffraction Measurements to Characterize Early-stage Evolution of Irradiation-Induced Defects in Ceramics, Acta Mater. 193 (2020) 61-70.
  25. Z. Hua, T. Yao, A. Khanolkar, X. Ding, K. Gofryk, L. He, M. Benson, D. Hurley: Intragranular thermal transport in U50Zr, J. Nucl. Mater. 534 (2020) 152145.
  26. A. Ronne, L. He, D. Dolzhnikov, Y. Xie, M. Ge, P. Halstenberg, Y. Wang, B.T. Manard, X. Xiao, W.-K. Lee, K. Sasaki, S.M. Mahurin, Y.K. Chen-Wiegart, Revealing 3D Morphological and Chemical Evolution Mechanisms of Metals in Molten Salt by Multimodal Microscopy, ACS App. Mater. Inter. 12 (2020) 17321-17333.
  27. S. Johns, L. He, J.J. Kane, W.E. Windes, R. Ubic: Experimental Evidence for “Buckle, Ruckle and Tuck" in Neutron Irradiated Graphite, Carbon, 159 (2020) 119-121.
  28. A. Cheniour, M. Tonks, B. Gong, T. Yao, L. He, J. Harp, J. Lian, B. Beeler, Y. Zhang: Development of A Grain Growth Model for U3Si2 using Experimental Data, Phase Field Simulation and Molecular Dynamics, J. Nucl. Mater., 532 (2020) 152069.
  29. T. Yao, A. Wagner, X. Liu, A. El-Azab, J. Harp, J. Gan, D. Hurley, M. Benson, L. He: On Spinodal-like Phase Decomposition in U-50Zr Alloy, Materialia 9 (2020) 100592.
  30. F. Cappia, B.D. Miller, L. He, D.J. Murray, B.J. Frickey, J.D. Stanek, J. Harp: Electron Microscopy Characterization of Fast Reactor MOX Joint Oxyde-Gaine (JOG), J. Nucl. Mater. 531 (2020) 151964.
  31. X. Liu, L. He, H. Yan, M. Bachhav, J. Stubbins: A Transmission Electron Microscopy Study of EBR-II Irradiated Austenitic Stainless Steel 304 and Nickel-Base Alloy X-750, J. Nucl. Mater., 528 (2020) 151851.
  32. Y. Bao, F. Kuang, Y. Sun, Y. Li, D. Wan, Z. Shen, D. Ma, L. He: A Simple Way to Make Pre-Stressed Ceramics with High Strength, J. Materiomics, 5 (2019) 657-662.
  33. M. Khafizov, J. Pakarinen, L. He, D.H. Hurley: Impact of Irradiation Induced Dislocation Loops on Thermal Conductivity in Ceramics, J. Am. Ceram. Soc., 102 (2019) 7533-7542.
  34. Y. Xie, M.T. Benson, L. He, J.A. King, R.D. Mariani, and D.J. Murray, Diffusion Behavior between Metallic Fuel Alloys with Pd Addition and Fe, J. Nucl. Mater., 518 (2019) 287-297.
  35. Z. Yu, C. Zhang, P.M. Voyles, L. He, X. Liu, K. Nygren, and A. Couet, Microstructure and Microchemistry Study of Irradiation-Induced Precipitates in Proton Irradiated ZrNb Alloys, Acta Mater., 178 (2019) 228-240.
  36. S.T. Nguyen, T. Nakayama, H. Suematsu, H. Iwasawa, T. Suzuki, Y. Otsuka, L. He, T. Takahashi, and K. Niihara, Self-healing Behavior and Strength Recovery of Ytterbium Disilicate Ceramic Reinforced with Silicon Carbide Nanofillers, J. Eur. Ceram. Soc., 39 (2019) 3139-3152.
  37. M.T. Benson, Y. Xie, L. He, K.R. Tolman, J.A. King, J.M. Harp, R.D. Mariani, B.J. Hernandez, D.J. Murray, and B.D. Miller: Microstructural Characterization of Annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln, J. Nucl. Mater., 518 (2019) 287-297.
  38. T. Yao, B. Gong, L. He, Y. Miao, J. Harp, M. Tonks, and J. Lian: In-Situ TEM Study of the Ion Irradiation Behavior of U3Si2 and U3Si5, J. Nucl. Mater., 511 (2018) 56-63.
  39. L. He, M. Bachhav, D.D. Keiser, J.W. Madden, E. Perez, B.D. Miller, J. Gan, W. Van Renterghem, A. Leenaers, and S. Van den Berghe: STEM-EDS/EELS and APT Characterization of ZrN Coatings on UMo Fuel Kernels, J. Nucl. Mater., 511 (2018) 174-182.
  40. M.T. Benson, L. He, J. King, R. Mariani, A.J. Winston, and J.M. Madden: Microstructural Characterization of As-Cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln, J. Nucl. Mater., 508 (2018) 310-318.
  41. J. Gan, C. Sun, L. He, Y. Zhang, C. Jiang, and Y. Gao: Thermal Stability of Helium Bubble Superlattice under TEM in-situ Heating, J. Nucl. Mater., 505 (2018) 207-211.
  42. C. Sun, D. Sprouster, K. Hattar, L. Ecker, L. He, Y. Gao, Y. Zhang, J. Gan: Formation of Gas Bubble Superlattice in Helium Implanted Bulk Molybdenum, Scripta Mater., 149 (2018) 26-30.
  43. M.T. Benson, L. He, J. King, R. Mariani: Characterization of Annealed U-10Zr-4Pd and U-10Zr-4Pd-5Ln Fuels, J. Nucl. Mater., 502 (2018) 106-112.
  44. R.E. Hoggan, L. He, J.M. Harp: Interdiffusion Behavior of U3Si2 with FeCrAl via Diffusion Couple Studies, J. Nucl. Mater., 502 (2018) 356-369.
  45. L. He, J.M. Harp, A.R. Wagner, R.E. Hoggan, and K.R. Tolman: Hydrothermal Synthesis of Silicon Oxide Clad Uranium Oxide Nanowires, J. Am. Ceram. Soc., 101 (2018) 1004-1008.
  46. T. Yao, B. Gong, L. He, J. Harp, M. Tonks, J. Lian: Radiation-induced Grain Subdivision and Bubble Formation in U3Si2 at LWR Temperature, J. Nucl. Mater., 498 (2018) 169-175.
  47. L. He, X.M. Bai, J. Pakarinen, B. Jaques, J. Gan, A.T. Nelson, A. El-Azab, and T.R. Allen: Bubble Evolution in Kr-irradiated UO2 during Annealing, J. Nucl. Mater., 496 (2017) 242-250.
  48. S.T. Nguyen, T. Nakayama, H. Suematsu, T. Suzuki, L. He, H.-B. Cho, and K. Niihara: Strength Improvement and Purification of Yb2Si2O7-SiC Nanocomposites by Surface Oxidation Treatment, J. Am. Ceram. Soc., 100 (2017) 3122-3131.
  49. L. He, J.M. Harp, R.E. Hoggan, and A.R. Wagner: Microstructure Studies of Interdiffusion Behavior of U3Si2/Zircaloy-4 at 800 and 100°C, J. Nucl. Mater., 486 (2017) 274-282.
  50. D.J. Tallman, L. He, J. Gan, El'ad N. Caspi, E.N. Hoffman, and M.W. Barsoum: Effect of Neutron Irradiation of Ti3SiC2 and Ti3AlC2 in the 121-1085°C Temperature Range, J. Nucl. Mater., 484 (2017) 120-134.
  51. G. Zheng, L. He, D. Carpenter, and K. Sridharan: Corrosion-induced Microstructural Developments in 316 Stainless Steel during Exposure to Molten Li2BeF4 (FLiBe) Salt, J. Nucl. Mater., 482 (2016) 147-155.
  52. M. Khafizov, J. Pakarrinen, L. He, H.B. Henderson, M.V. Manuel, B. Jacques, D.P. Butt, A. El-Azab, D. Hurley: Subsurface Imaging of Grain Microstructure Using Picosecond Ultrasonics, Acta Mater., 112 (2016) 209-215.
  53. D.J. Tallman, L. He, B.L. Garcia-Diaz, E.N. Hoffman, G. Kohse, R.L. Sindelar, and M.W. Barsoum: Effect of Neutron Irradiation on Defect Evolution in Ti3SiC2 and Ti2AlC, J. Nucl. Mater., 468 (2016) 194-206.
  54. G. Zheng, B. Kelleher, L. He, G. Cao, M. Anderson, T. Allen, and K. Sridharan: High-Temperature Corrosion of UNS N10003 in Molten Li2BeF4 (FLiBe) Salt, Corrosion, 71 (2015) 1257-1266.
  55. J. Pakarinen, L. He, A.-R. Hassan, M. Gupta, A. El-Azab, and T.R. Allen: Annealing-Induced Lattice Recovery in Room-Temperature Xenon Irradiated CeO2: X-ray Diffraction and Electron Energy Loss Spectroscopy Experiments, J. Mater. Res., 30 (2015) 1555-1562.
  56. L. He, B. Valderrama, A-R. Hassan, J. Yu, M. Gupta, J. Pakarinen, H.B. Henderson, J. Gan, M.A. Kirk, A.T. Nelson, M.V. Manuel, A. El-Azab, and T.R. Allen: Bubble Formation and Kr Distribution in Kr-irradiated UO2, J. Nucl. Mater., 456 (2015) 125-132.
  57. L. He, M.A. Kirk, M. Gupta, J. Pakarinen, J. Gan, A.T. Nelson, A. El-Azab, and T.R. Allen: In Situ TEM Observation of Dislocation Evolution in Polycrystalline UO2, JOM, 66 (2014) 2553-2561.
  58. B. Valderrama, L. He, H.B. Henderson, J. Pakarinen, B. Jacques, J. Gan, D.P. Butt, T.R. Allen, and M.V. Manuel: Effect of Grain Boundaries on Krypton Segregation Behavior in Irradiated Uranium Dioxide, JOM, 66 (2014) 2562-2568.
  59. J. Pakarinen, M. Khafizov, L. He, C. Wetteland, J. Gan, A. Nelson, D.H. Hurley, A. El-Azab, and T.R. Allen: Microstructures and Thermal Conductivity Evolution in 3.9 MeV He2+ Irradiated Depleted UO2, J. Nucl. Mater, 454 (2014) 283-289.
  60. L. He, J. Pakarinen, M.A. Kirk, J. Gan, A.T. Nelson, A. El-Azab, and T.R. Allen: Microstructure Evolution in Xe-Irradiated UO2 at Room Temperature, Nucl. Instrum. Meth. B, 330 (2014) 55-60.
  61. L. He, P. Roman, B. Leng, K. Sridharan, M. Anderson, and T.R. Allen: Corrosion Behavior of an Alumina Forming Austenitic Steel Exposed to Supercritical Carbon Dioxide, Corros. Sci., 82 (2014) 67-76.
  62. M. Khafizov, I.-W. Park, A. Chernatynskiy, L. He, J. Lin, J.J. Moore, D. Swank, T. Lillo, S.R. Phillpot, A. El-Azab, and D. Hurley: Thermal Conductivity in Nanocrystalline Ceria Thin Films, J. Am. Ceram. Soc., 97 (2014) 562-569.
  63. J. Pakarinen, L. He, M. Gupta, A. Nelson, A. El-Azab, and T.R. Allen: 2.6 MeV Proton Irradiation Effects on the Surface Integrity of Depleted UO2, Nucl. Instrum. Meth. B, 319 (2014) 100-106.
  64. L. He, M. Gupta, C.A. Yablinsky, J. Gan, M.A. Kirk, X.M. Bai, J. Pakarinen, and T.R. Allen: In Situ TEM Observation of Dislocation Evolution in Kr-Irradiated UO2 Single Crystal, J. Nucl. Mater., 443 (2013) 71-77.
  65. L. He, C.A. Yablinsky, M. Gupta, J. Gan, M.A. Kirk, and T.R. Allen: Transmission Electron Microscopy Investigation of Krypton Bubbles in Polycrystalline CeO2, Nucl. Tech., 182 (2013) 164-169. 

Invited Speaker at Conferences and University Seminars: Materials Science & Technology (MS&T 10/2021), Microscopy & Microanalysis (M&M 8/2021), The Materials Research Society (MRS) Fall Meeting (12/2019), The American Vacuum Society (AVS) International Symposium & Exhibition (10/2019), The American Chemical Society (ACS) National Meeting (8/2019), The Minerals, Metals and Materials Society (TMS) Meeting (2/2017, 3/2019, 3/2020), Advances in Structural and Chemical Imaging (ASCI) Meeting (5/2016); The University of Tennessee-Knoxville (12/2016), The Ohio State University (10/2019), The University of Utah (3/2020), University of Nebraska-Lincoln (11/2020), The Pennsylvania State University (3/2021)


Laboratory Director's 2020 Exceptional Scientific Achievement Award, Idaho National Laboratory

Research Interests:

Materials behavior in extreme environments, with a focus on environmental degradation of materials in nuclear power systems. Understanding how the processing and radiation/corrosion environments change the microstructure of materials and its effects on the mechanical, corrosion and thermal properties of materials.​​
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