Lingfeng He

Yang, J., Hawkins, L., Shang, Z., Tsai, B. K., He, L., Lu, Y., … Lou, X. (2024, March 1). Dislocation channel broadening-A new mechanism to improve irradiation-assisted stress corrosion cracking resistance of additively manufactured 316 L stainless steel. ACTA MATERIALIA, Vol. 266. https://doi.org/10.1016/j.actamat.2024.119650

Mazumder, S. K., Bawane, K., Mann, J. M., French, A., Shao, L., He, L., & El-Azab, A. (2023). Evolution of dislocation loops and voids in post-irradiation annealed ThO<sub>2</sub>: A combined <i>in-situ</i> TEM and cluster dynamics investigation. JOURNAL OF NUCLEAR MATERIALS, 586. https://doi.org/10.1016/j.jnucmat.2023.154686

Yang, J., Hawkins, L., He, L., Mahmood, S., Song, M., Schulze, K., & Lou, X. (2023). Intragranular irradiation-assisted stress corrosion cracking (IASCC) of 316L stainless steel made by laser direct energy deposition additive manufacturing: Delta ferrite-dislocation channel interaction. JOURNAL OF NUCLEAR MATERIALS, 577. https://doi.org/10.1016/j.jnucmat.2023.154305

Yu, Z., Bachhav, M., Teng, F., He, L., Dubey, M., & Couet, A. (2023). STEM/EDS and APT study on the microstructure and microchemistry of neutron irradiated ZIRLOTM. Journal of Nuclear Materials, 573, 154139. https://doi.org/10.1016/j.jnucmat.2022.154139

Liu, X., Bawane, K., Zheng, X., Ge, M., Halstenberg, P., Maltsev, D. S., … Chen-Wiegart, Y.-chen K. (2023). Temperature-Dependent Morphological Evolution during Corrosion of the Ni-20Cr Alloy in Molten Salt Revealed by Multiscale Imaging. ACS APPLIED MATERIALS & INTERFACES, 15(10), 13772–13782. https://doi.org/10.1021/acsami.2c23207

Hawkins, L., Yang, J., Song, M., Schwen, D., Zhang, Y., Shao, L., … He, L. (2023). The effect of secondary phases on microstructure and irradiation damage in an as-built additively manufactured 316 L stainless steel with a hafnium compositional gradient. JOURNAL OF NUCLEAR MATERIALS, 587. https://doi.org/10.1016/j.jnucmat.2023.154708

Thomas, J., Liu, X., He, L., Murray, D., Teng, F., Kombaiah, B., … Okuniewski, M. A. (2023). Transmission electron microscopy investigation of phase transformation and fuel constituent redistribution in neutron irradiated U-10wt.%Zr fuel. JOURNAL OF NUCLEAR MATERIALS, 581. https://doi.org/10.1016/j.jnucmat.2023.154443

Song, M., Yang, J., Liu, X., Hawkins, L. R., Jiao, Z., He, L., … Lou, X. (2023). Void swelling in additively manufactured 316L stainless steel with hafnium composition gradient under self-ion irradiation. Journal of Nuclear Materials, 578, 154351. https://doi.org/10.1016/j.jnucmat.2023.154351

Deskins, W. R., Khanolkar, A., Mazumder, S., Dennett, C. A., Bawane, K., Hua, Z., … El-Azab, A. (2022). A combined theoretical-experimental investigation of thermal transport in low-dose irradiated thorium dioxide. Acta Materialia, 241, 118379. https://doi.org/10.1016/j.actamat.2022.118379

Copeland-Johnson, T. M., Murray, D. J., Cao, G., & He, L. (2022). Assessing the interfacial corrosion mechanism of Inconel 617 in chloride molten salt corrosion using multi-modal advanced characterization techniques. Frontiers in Nuclear Engineering, 1. https://doi.org/10.3389/fnuen.2022.1049693

Ditter, A. S., Smiles, D. E., Lussier, D., Altman, A. B., Bachhav, M., He, L., … Shuh, D. K. (2022). Chemical and elemental mapping of spent nuclear fuel sections by soft X-ray spectromicroscopy. Journal of Synchrotron Radiation, 29(1), 67–79. https://doi.org/10.1107/S1600577521012315

Yang, J., Hawkins, L., Song, M., He, L., Bachhav, M., Pan, Q., … Lou, X. (2022). Compositionally graded specimen made by laser additive manufacturing as a high-throughput method to study radiation damages and irradiation-assisted stress corrosion cracking. Journal of Nuclear Materials, 560, 153493. https://doi.org/10.1016/j.jnucmat.2021.153493

Chauhan, V. S., Ferrigno, J., Adnan, S., Pakarinen, J., He, L., Hurley, D. H., & Khafizov, M. (2022). Comprehensive characterization of irradiation induced defects in ceria: Impact of point defects on vibrational and optical properties. Journal of Applied Physics. https://doi.org/10.1063/5.0099189

He, L., Yao, T., Bawane, K., Jin, M., Jiang, C., Liu, X., … Khafizov, M. (2022). Dislocation loop evolution in Kr‐irradiated ThO2. Journal of the American Ceramic Society. https://doi.org/10.1111/jace.18478

Gabriel, A., Hawkins, L., French, A., Li, Y., Hu, Z., He, L., … Shao, L. (2022). Effect of dpa rate on the temperature regime of void swelling in ion-irradiated pure chromium. Journal of Nuclear Materials, 561, 153519. https://doi.org/10.1016/j.jnucmat.2022.153519

Sure, J., Gill, S. k, Wang, Y., Bawane, K. K., He, L., Halstenberg, P., … Sasaki, K. (2022). Electrochemical noise studies on localized corrosion of Ni and Ni-20Cr in molten ZnCl2. Electrochimica Acta, 431, 141126. https://doi.org/10.1016/j.electacta.2022.141126

Vijayan, S., Bawane, K., Giulia Dilemma, F., He, L., Fink, C., & Jinschek, J. R. (2022). In situ</i> TEM Observations of Thermally Activated Phenomena in Materials Under Far-From-Equilibrium Conditions. Microscopy and Microanalysis, 28(S1), 1844–1846. https://doi.org/10.1017/S1431927622007255

Wang, Y., Liu, X., Murray, D. J., Teng, F., Jiang, W., Bachhav, M., … He, L. (2022). Measurement of grain boundary strength of Inconel X-750 superalloy using in-situ micro-tensile testing techniques in FIB/SEM system. Materials Science and Engineering: A, 849, 143475. https://doi.org/10.1016/j.msea.2022.143475

Pena, M., Morell-Pacheco, A., Shiau, C.-H., Kombaiah, B., He, L., Hawkins, L., … Shao, L. (2022). Microstructural changes of proton irradiated Hastelloy-N and in situ micropillar compression testing of one single grain at different local damage levels. Journal of Nuclear Materials. https://doi.org/10.1016/j.jnucmat.2022.153939

Parkin, C., Moorehead, M., Elbakhshwan, M., Zhang, X., Xiu, P., He, L., … Couet, A. (2022). Phase stability, mechanical properties, and ion irradiation effects in face-centered cubic CrFeMnNi compositionally complex solid-solution alloys at high temperatures. Journal of Nuclear Materials, 565, 153733. https://doi.org/10.1016/j.jnucmat.2022.153733

Sun, Y., Wu, T., Bao, Y., Li, Y., Wan, D., Li, K., & He, L. (2022). Preparation and strengthening mechanism of prestressed ceramic tile components. International Journal of Applied Ceramic Technology. https://doi.org/10.1111/ijac.13757

Field, K. G., Patki, P., Sharaf, N., Sun, K., Hawkins, L., Lynch, M., … Field, C. R. (2022). Real-time, On-Microscope Automated Quantification of Features in Microcopy Experiments Using Machine Learning and Edge Computing. Microscopy and Microanalysis, 28(S1), 2046–2048. https://doi.org/10.1017/S1431927622007929

Yang, J., Liu, X., Song, M., He, L., Bankson, S., Hamilton, M., … Lou, X. (2022). Sensitization, desensitization, and carbide evolution of Alloy 800H made by laser powder bed fusion. Additive Manufacturing, 50, 102547. https://doi.org/10.1016/j.addma.2021.102547

Herrmann, S. D., Zhao, H., Bawane, K. K., He, L., Tolman, K. R., & Pu, X. (2022). Synthesis and characterization of uranium trichloride in alkali-metal chloride media. Journal of Nuclear Materials, 565, 153728. https://doi.org/10.1016/j.jnucmat.2022.153728

Hurley, D. H., El-Azab, A., Bryan, M. S., Cooper, M. W. D., Dennett, C. A., Gofryk, K., … Wharry, J. P. (2022). Thermal Energy Transport in Oxide Nuclear Fuel. Chemical Reviews. https://doi.org/10.1021/acs.chemrev.1c00262

Jiang, C., He, L., Dennett, C. A., Khafizov, M., Mann, J. M., & Hurley, D. H. (2022). Unraveling small-scale defects in irradiated ThO2 using kinetic Monte Carlo simulations. Scripta Materialia. https://doi.org/10.1016/j.scriptamat.2022.114684

Bawane, K., Liu, X., Gakhar, R., Woods, M., Ge, M., Xiao, X., … He, L. (2022). Visualizing time-dependent microstructural and chemical evolution during molten salt corrosion of Ni-20Cr model alloy using correlative quasi in situ TEM and in situ synchrotron X-ray nano-tomography. Corrosion Science, 195, 109962. https://doi.org/10.1016/j.corsci.2021.109962

He, L., Hawkins, L., Yang, J., Liu, X., Song, M., Lou, X., … Schwen, D. (2021). Advanced Characterization of Additively Manufactured 316L Stainless Steel for Nuclear Applications. Microscopy and Microanalysis, 27(S1), 2160–2161. https://doi.org/10.1017/S1431927621007789

Dennett, C. A., Deskins, W. R., Khafizov, M., Hua, Z., Khanolkar, A., Bawane, K., … El-Azab, A. (2021). An integrated experimental and computational investigation of defect and microstructural effects on thermal transport in thorium dioxide. Acta Materialia, 213, 116934. https://doi.org/10.1016/j.actamat.2021.116934

Bawane, K., Manganaris, P., Wang, Y., Sure, J., Ronne, A., Halstenberg, P., … He, L. (2021). Determining oxidation states of transition metals in molten salt corrosion using electron energy loss spectroscopy. Scripta Materialia, 197, 113790. https://doi.org/10.1016/j.scriptamat.2021.113790

Xiu, P., Jin, M., Bawane, K., Tyburska-Püschel, B., Jaques, B. J., Field, K. G., … He, L. (2021). Dislocation Loops in Proton Irradiated Uranium-Nitrogen-Oxygen System. Journal of Nuclear Materials, 557, 153244. https://doi.org/10.1016/j.jnucmat.2021.153244

Yan, H., Liu, X., He, L., & Stubbins, J. (2021). Early-stage microstructural evolution and phase stability in neutron-irradiated ferritic-martensitic steel T91. Journal of Nuclear Materials, 557, 153207. https://doi.org/10.1016/j.jnucmat.2021.153207

Yang, J., Song, M., Hawkins, L. R., Liu, X., He, L., & Lou, X. (2021). Effects of heat treatment on corrosion fatigue and stress corrosion crack growth of additive-manufactured Alloy 800H in high-temperature water. Corrosion Science, 191, 109739. https://doi.org/10.1016/j.corsci.2021.109739

Xiao, Z., He, L., & Bai, X.-M. (2021). First principle studies of effects of solute segregation on grain boundary strength in Ni-based alloys. Journal of Alloys and Compounds, 874, 159795. https://doi.org/10.1016/j.jallcom.2021.159795

Liu, X., Capriotti, L., Yao, T., Harp, J. M., Benson, M. T., Wang, Y., … He, L. (2021). Fuel-cladding chemical interaction of a prototype annular U-10Zr fuel with Fe-12Cr ferritic/martensitic HT-9 cladding. Journal of Nuclear Materials, 544, 152588. https://doi.org/10.1016/j.jnucmat.2020.152588

Khanolkar, A., Yao, T., Hua, Z., Dennett, C. A., Reese, S. J., Schley, R. S., … Hurley, D. H. (2021). In situ monitoring of microstructure evolution during thermal processing of uranium-zirconium alloys using laser-generated ultrasound. Journal of Nuclear Materials, 4, 153005. https://doi.org/10.1016/j.jnucmat.2021.153005

Chauhan, V. S., Pakarinen, J., Yao, T., He, L., Hurley, D. H., & Khafizov, M. (2021). Indirect characterization of point defects in proton irradiated ceria. Materialia, 15, 101019. https://doi.org/10.1016/j.mtla.2021.101019

Gill, S. K., Sure, J., Wang, Y., Layne, B., He, L., Mahurin, S., … Sasaki, K. (2021). Investigating corrosion behavior of Ni and Ni-20Cr in molten ZnCl2. Corrosion Science, 179, 109105. https://doi.org/10.1016/j.corsci.2020.109105

Bachhav, M., Kane, J., Teng, F., Cappia, F., & He, L. (2021). Isotopic Analysis of Irradiated Ceramic Fuel for Burnup and Microchemical Assessment Using Atom Probe Tomography. Microscopy and Microanalysis, 27(S1), 416–417. https://doi.org/10.1017/S1431927621002002

Yuan, R., Zhang, J., He, L., & Zuo, J.-M. (2021). Machine Learning Based Precision Orientation and Strain Mapping from 4D Diffraction Datasets. Microscopy and Microanalysis, 27(S1), 1276–1278. https://doi.org/10.1017/S1431927621004785

Lemma, F. G. D., Jensen, C. B., Kane, J. J., Chen, W.-Y., Liu, X., Capriotti, L., … Wachs, D. (2021). Metallic Fast Reactor Separate Effect Studies for Fuel Safety. Journal of Nuclear Engineering and Radiation Science, 7(4). https://doi.org/10.1115/1.4049721

Yu, Z., Bachhav, M., Teng, F., He, L., & Couet, A. (2021). Nanoscale redistribution of alloying elements in high-burnup AXIOM-2 (X2®) and their effects on in-reactor corrosion. Corrosion Science, 190, 109652. https://doi.org/10.1016/j.corsci.2021.109652

He, L., Khafizov, M., Jiang, C., Tyburska-Püschel, B., Jaques, B. J., Xiu, P., … Gan, J. (2021). Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation. Acta Materialia. https://doi.org/10.1016/j.actamat.2021.116778

Yan, H., Liu, X., He, L., & Stubbins, J. (2021). Phase stability and microstructural evolution in neutron-irradiated ferritic-martensitic steel HT9. Journal of Nuclear Materials, 557, 153252. https://doi.org/10.1016/j.jnucmat.2021.153252

Pakarinen, J., He, L., Gan, J., Nelson, A. T., El-Azab, A., Khafizov, M., & Allen, T. R. (2021). Proton irradiation-induced blistering in UO2. MRS Advances, 11. https://doi.org/10.1557/s43580-021-00149-3

Liu, X., Cinbiz, M. N., Kombaiah, B., He, L., Teng, F., & Lacroix, E. (2021). Structure of the pellet-cladding interaction layer of a high-burnup Zr-Nb-O nuclear fuel cladding. Journal of Nuclear Materials, 556, 153196. https://doi.org/10.1016/j.jnucmat.2021.153196

Bawane, K., Liu, X., Yao, T., Khafizov, M., French, A., Mann, J. M., … He, L. (2021). TEM Characterization of Dislocation Loops in Proton Irradiated Single Crystal ThO2. Journal of Nuclear Materials, 4, 152998. https://doi.org/10.1016/j.jnucmat.2021.152998

Deskins, W. R., Hamed, A., Kumagai, T., Dennett, C. A., Peng, J., Khafizov, M., … El-Azab, A. (2021). Thermal conductivity of ThO2: Effect of point defect disorder. Journal of Applied Physics. https://doi.org/10.1063/5.0038117

Yuan, R., Zhang, J., He, L., & Zuo, J.-M. (2021). Training artificial neural networks for precision orientation and strain mapping using 4D electron diffraction datasets. Ultramicroscopy, 3, 113256. https://doi.org/10.1016/j.ultramic.2021.113256

Yao, T., Sen, A., Wagner, A., Teng, F., Bachhav, M., EI-Azab, A., … He, L. (2021). Understanding spinodal and binodal phase transformations in U-50Zr. Materialia, 16, 101092. https://doi.org/10.1016/j.mtla.2021.101092

Liu, X., He, L., Yan, H., Bachhav, M., & Stubbins, J. F. (2020). A transmission electron microscopy study of EBR-II neutron-irradiated austenitic stainless steel 304 and nickel-base alloy X-750. Journal of Nuclear Materials, 528, 151851. https://doi.org/10.1016/j.jnucmat.2019.151851

Bachhav, M., He, L., Kane, J., Liu, X., Gan, J., & Vurpiliot, F. (2020). Atom Probe Tomography for Burnup and Fission Product Analysis for Nuclear Fuels. Microscopy and Microanalysis, 26(S2), 3086–3088. https://doi.org/10.1017/S1431927620023776

Khafizov, M., Riyad, M. F., Wang, Y., Pakarinen, J., He, L., Yao, T., … Hurley, D. (2020). Combining mesoscale thermal transport and x-ray diffraction measurements to characterize early-stage evolution of irradiation-induced defects in ceramics. Acta Materialia, 193, 61–70. https://doi.org/10.1016/j.actamat.2020.04.018

Wang, Y., Yao, T., Xi, F., Lei, P., Guo, X., He, L., … Lian, J. (2020). Degradation mechanism of lead-vanado-iodoapatite in NaCl solution. Corrosion Science, 172, 108720. https://doi.org/10.1016/j.corsci.2020.108720

Cheniour, A., Tonks, M. R., Gong, B., Yao, T., He, L., Harp, J. M., … Lian, J. (2020). Development of a grain growth model for U3Si2 using experimental data, phase field simulation and molecular dynamics. Journal of Nuclear Materials, 532, 152069. https://doi.org/10.1016/j.jnucmat.2020.152069

Zhang, Y., Lin, Y., He, L., Murugesan, V., Pawar, G., Sivakumar, B. M., … Li, B. (2020). Dual Functional Ni<sub>3</sub>S<sub>2</sub>@Ni Core–Shell Nanoparticles Decorating Nanoporous Carbon as Cathode Scaffolds for Lithium–Sulfur Battery with Lean Electrolytes. ACS Applied Energy Materials, 3(5), 4173–4179. https://doi.org/10.1021/acsaem.0c00568

Yu, Z., Kim, T., Bachhav, M., Liu, X., He, L., & Couet, A. (2020). Effect of proton pre-irradiation on corrosion of Zr-0.5Nb model alloys with different Nb distributions. Corrosion Science, 173, 108790. https://doi.org/10.1016/j.corsci.2020.108790

Cappia, F., Miller, B. D., Aguiar, J. A., He, L., Murray, D. J., Frickey, B. J., … Harp, J. M. (2020). Electron microscopy characterization of fast reactor MOX Joint Oxyde-Gaine (JOG). Journal of Nuclear Materials, 531, 151964. https://doi.org/10.1016/j.jnucmat.2019.151964

Hoffman, A., Arivu, M., Wen, H., He, L., Sridharan, K., Wang, X., … Wu, Y. (2020). Enhanced Resistance to Irradiation Induced Ferritic Transformation in Nanostructured Austenitic Steels. Materialia. https://doi.org/10.1016/j.mtla.2020.100806

Johns, S., He, L., Kane, J. J., Windes, W. E., Ubic, R., & Karthik, C. (2020). Experimental evidence for ‘buckle, ruck and tuck’ in neutron irradiated graphite. Carbon, 159, 119–121. https://doi.org/10.1016/j.carbon.2019.12.028

Johns, S., He, L., Bustillo, K., Windes, W. E., Ubic, R., & Karthik, C. (2020). Fullerene-like defects in high-temperature neutron-irradiated nuclear graphite. Carbon, 166, 113–122. https://doi.org/10.1016/j.carbon.2020.05.028

Gill, S. K., Topsakal, M., Jossou, E., Huang, X., Hattar, K., Mausz, J., … Ecker, L. (2020). Impact of krypton irradiation on a single crystal tungsten: Multi-modal X-ray imaging study. Scripta Materialia, 188, 296–301. https://doi.org/10.1016/j.scriptamat.2020.07.024

Parkin, C., Moorehead, M., Elbakhshwan, M., Hu, J., Chen, W.-Y., Li, M., … Couet, A. (2020). In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation. Acta Materialia, 198, 85–99. https://doi.org/10.1016/j.actamat.2020.07.066

Hua, Z., Yao, T., Khanolkar, A., Ding, X., Gofryk, K., He, L., … Hurley, D. (2020). Intragranular thermal transport in U–50Zr. Journal of Nuclear Materials, 534, 152145. https://doi.org/10.1016/j.jnucmat.2020.152145

Yao, T., Wagner, A. R., Liu, X., EI-Azab, A., Harp, J. M., Gan, J., … He, L. (2020). On spinodal-like phase decomposition in U–50Zr alloy. Materialia. https://doi.org/10.1016/j.mtla.2020.100592

Ronne, A., He, L., Dolzhnikov, D., Xie, Y., Ge, M., Halstenberg, P., … Chen-Wiegart, Y.-chen K. (2020). Revealing 3D Morphological and Chemical Evolution Mechanisms of Metals in Molten Salt by Multimodal Microscopy. ACS Applied Materials & Interfaces, 12(15), 17321–17333. https://doi.org/10.1021/acsami.9b19099

Couet, A., He, L., Bachhav, M., & Yu, Z. (2020). TEM and APT Characterization of Neutron Irradiated AXIOM-2(X2). Presented at the 2020 ANS Virtual Winter Meeting. https://doi.org/10.13182/t123-33175

Chen, T., He, L., Cullison, M. H., Hay, C., Burns, J., Wu, Y., & Tan, L. (2020). The correlation between microstructure and nanoindentation property of neutron-irradiated austenitic alloy D9. Acta Materialia, 195, 433–445. https://doi.org/10.1016/j.actamat.2020.05.020

Dennett, C. A., Hua, Z., Khanolkar, A., Yao, T., Morgan, P. K., Prusnick, T. A., … Hurley, D. H. (2020). The influence of lattice defects, recombination, and clustering on thermal transport in single crystal thorium dioxide. APL Materials. https://doi.org/10.1063/5.0025384

Yao, T., Capriotti, L., Harp, J. M., Liu, X., Wang, Y., Teng, F., … He, L. (2020). α-U and ω-UZr2 in neutron irradiated U-10Zr annular metallic fuel. Journal of Nuclear Materials, 542, 152536. https://doi.org/10.1016/j.jnucmat.2020.152536

Bao, Y., Kuang, F., Sun, Y., Li, Y., Wan, D., Shen, Z., … He, L. (2019). A simple way to make pre-stressed ceramics with high strength. Journal of Materiomics, 5(4), 657–662. https://doi.org/10.1016/j.jmat.2019.06.001

Benson, M. T., Xie, Y., He, L., & King, J. A. (2019). Characterization of U-Pu-Zr alloys with Pd as a minor additive. Transactions of the American Nuclear Society, 120.

Xie, Y., Benson, M. T., He, L., King, J. A., Mariani, R. D., & Murray, D. J. (2019). Diffusion Behavior between Metallic Fuel Alloys with Pd Addition and Fe. Journal of Nuclear Materials, 525, 111–124. https://doi.org/10.1016/j.jnucmat.2019.07.028

Xie, Y., Benson, M. T., He, L., & King, J. A. (2019). Diffusion behaviors between Fe and Pd-containing metallic fuel. Transactions of the American Nuclear Society, 120(1), 412–413.

Khafizov, M., Pakarinen, J., He, L., & Hurley, D. H. (2019). Impact of irradiation induced dislocation loops on thermal conductivity in ceramics. Journal of the American Ceramic Society, 102(12), 7533–7542. https://doi.org/10.1111/jace.16616

Palmer, A. J., Holbrook, M. R., Jaoude, A. A., Core, G. M., Cao, G., Marsden, K. C., … Calderoni, P. (2019). Irradiation Testing Strategy for Commercialization of a Molten Chloride Fast Reactor System.

Benson, M. T., Xie, Y., He, L., Tolman, K. R., King, J. A., Harp, J. M., … Miller, B. D. (2019). Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln. Journal of Nuclear Materials, 518, 287–297. https://doi.org/10.1016/j.jnucmat.2019.03.014

Yu, Z., Zhang, C., Voyles, P. M., He, L., Liu, X., Nygren, K., & Couet, A. (2019). Microstructure and microchemistry study of irradiation-induced precipitates in proton irradiated ZrNb alloys. Acta Materialia. https://doi.org/10.1016/j.actamat.2019.08.012

Nguyen, S. T., Nakayama, T., Suematsu, H., Iwasawa, H., Suzuki, T., Otsuka, Y., … Niihara, K. (2019). Self-healing behavior and strength recovery of ytterbium disilicate ceramic reinforced with silicon carbide nanofillers. Journal of the European Ceramic Society, 39(10), 3139–3152. https://doi.org/10.1016/j.jeurceramsoc.2019.03.040

He, L., Murray, D., Liu, X., Jiang, W., Bachhav, M., Bai, X., & Teysseyre, S. (2019). Small Scale Tensile Testing of Grain Boundary Strength of X-750 Alloy. Proceedings of 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Presented at the 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Boston, MA.

Bachhav, M., Gan, J., He, L., Miller, B., & Keiser, D. (2018). Challenges and Opportunities on Elucidating Irradiated Fuels with Atom Probe Tomography. Microscopy and Microanalysis, 24(S1), 2206–2207. https://doi.org/10.1017/s1431927618011510

Hoggan, R., Harp, J., & He, L. (2018). Evaluation of U3Si2 Fuel Pellets Sintered in an Argon vs. Vacuum Environment. Ceramic Transactions Series, 10, 21–26. https://doi.org/10.1002/9781119543299.ch3

Formation of tetragonal gas bubble superlattice in bulk molybdenum under helium ion implantation. (2018). Scripta Materialia. https://doi.org/https://doi.org/10.1016/j.scriptamat.2018.01.023

Sun, C., Sprouster, D. J., Hattar, K., Ecker, L. E., He, L., Gao, Y., … Gan, J. (2018). Formation of tetragonal gas bubble superlattice in bulk molybdenum under helium ion implantation. Scripta Materialia, 149, 26–30. https://doi.org/10.1016/j.scriptamat.2018.01.023

He, L., Harp, J. M., Wagner, A. R., Hoggan, R. E., & Tolman, K. R. (2018). Hydrothermal synthesis of silicon oxide clad uranium oxide nanowires. Journal of the American Ceramic Society. https://doi.org/10.1111/jace.15295

Yao, T., Gong, B., He, L., Miao, Y., Harp, J. M., Tonks, M., & Lian, J. (2018). In-situ TEM study of the ion irradiation behavior of U3Si2 and U3Si5. Journal of Nuclear Materials, 511, 56–63. https://doi.org/10.1016/j.jnucmat.2018.08.058

Hoggan, R. E., He, L., & Harp, J. M. (2018). Interdiffusion behavior of U3Si2 with FeCrAl via diffusion couple studies. Journal of Nuclear Materials, 502, 356–369. https://doi.org/10.1016/j.jnucmat.2017.10.057

Benson, M. T., He, L., King, J. A., & Mariani, R. D. (2018). Investigating Pd as a Potential Fuel Additive in a Transmutation Fuel to Control FCCI. Transactions of the American Nuclear Society, 118, 1379–1380.

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Zhang, H., Presser, V., Berthold, C., Nickel, K. G., Wang, X., Raisch, C., … Zhou, Y. (2010). Mechanisms and kinetics of the hydrothermal oxidation of bulk titanium silicon carbide. Journal of the American Ceramic Society, 93(4), 1148–1155. https://doi.org/10.1111/j.1551-2916.2009.03570.x

He, L.-F., Li, F.-Z., Lu, X.-P., Bao, Y.-W., & Zhou, Y.-C. (2010). Microstructure, mechanical, thermal, and oxidation properties of a Zr2[Al(Si)]4C5-SiC composite prepared by in situ reaction/hot-pressing. Journal of the European Ceramic Society, 30(11), 2147–2154. https://doi.org/10.1016/j.jeurceramsoc.2010.02.005

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Zhang, J., He, L., & Zhou, Y. (2009). Highly conductive and strengthened copper matrix composite reinforced by Zr2Al3C4 particulates. Scripta Materialia, 60(11), 976–979. https://doi.org/10.1016/j.scriptamat.2009.02.026

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Wu, L., He, L.-F., Bao, Y.-W., & Zhou, Y.-C. (2009). Tribological properties of a Zr2Al3C4 ceramic at ambient temperature. Journal of the American Ceramic Society, 92(1), 141–146. https://doi.org/10.1111/j.1551-2916.2008.02805.x

He, L. F., Zhong, H. B., Xu, J. J., Li, M. S., Bao, Y. W., Wang, J. Y., & Zhou, Y. C. (2009). Ultrahigh-temperature oxidation of Zr2Al3C4 via rapid induction heating. Scripta Materialia, 60(7), 547–550. https://doi.org/10.1016/j.scriptamat.2008.12.002

He, L.-F., Bao, Y.-W., & Zhou, Y.-C. (2009). Zirconium aluminum carbides: New precursors for synthesizing ZrO 2-Al2O3 composites. Journal of the American Ceramic Society, 92(11), 2751–2758. https://doi.org/10.1111/j.1551-2916.2009.03281.x

Lin, Z. J., He, L. F., Wang, J. Y., Li, M. S., Bao, Y. W., & Zhou, Y. C. (2008). Atomic-scale microstructure and elastic properties of quaternary Zr-Al-Si-C ceramics. Acta Materialia, 56(9), 2022–2031. https://doi.org/10.1016/j.actamat.2007.12.055

He, L. F., Lin, Z. J., Wang, J. Y., Bao, Y. W., & Zhou, Y. C. (2008). Crystal structure and theoretical elastic property of two new ternary ceramics Hf3Al4C6 and Hf2Al4C5. Scripta Materialia, 58(8), 679–682. https://doi.org/10.1016/j.scriptamat.2007.12.002

He, L. F., Bao, Y. W., Li, M. S., Wang, J. Y., & Zhou, Y. C. (2008). Improving the high-temperature oxidation resistance of Zr2 Al3C4 by silicon pack cementation. Journal of Materials Research, 23(8), 2275–2282. https://doi.org/10.1557/jmr.2008.0285

Hu, C., Li, F., He, L., Liu, M., Zhang, J., Wang, J., … Zhou, Y. (2008). In Situ. Journal of the American Ceramic Society, 91(7), 2258–2263. https://doi.org/10.1111/j.1551-2916.2008.02424.x

Hu, C., He, L., Liu, M., Wang, X., Wang, J., Li, M., … Zhou, Y. (2008). In situ reaction synthesis and mechanical properties of V2AlC. Journal of the American Ceramic Society, 91(12), 4029–4035. https://doi.org/10.1111/j.1551-2916.2008.02774.x

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