Lingfeng He

Also known as: Ling-Feng He

ceramics, nanocomposites, nuclear materials, radiation damage, corrosion

Dr. Lingfeng He received his B.S. in Metallurgical Engineering from the Central South University in 2003 and a Ph.D. in Materials Science from the Chinese Academy of Sciences in 2009. He was a postdoctoral researcher and assistant scientist at Nagaoka University of Technology, Japan, and the University of Wisconsin-Madison before joining Idaho National Laboratory (INL) as a staff scientist in 2014. He was a distinguished staff scientist (Level V) and High-Resolution Materials Characterization group lead at INL prior to joining NC State as an Associate Professor of Nuclear Engineering in August 2022. Dr. He is interested in materials behavior in radiation, corrosion, stress and ultrahigh temperature extremes. His main research areas include ceramics and composites, nuclear fuels, structural materials, spent nuclear fuels, nuclear waste forms, synthesis/manufacturing, advanced characterization, radiation effects, molten salt corrosion, oxidation, mechanical properties and thermal properties.

Works (167)

Updated: April 4th, 2024 15:09

2024 article

Dislocation channel broadening-A new mechanism to improve irradiation-assisted stress corrosion cracking resistance of additively manufactured 316 L stainless steel

Yang, J., Hawkins, L., Shang, Z., Tsai, B. K., He, L., Lu, Y., … Lou, X. (2024, March 1). ACTA MATERIALIA, Vol. 266.

author keywords: 316 L stainless steel; Additive manufacturing; Irradiation-assisted stress corrosion cracking (IASCC); Dislocation channel broadening; Grain boundary; Radiation damage; Local deformation
Sources: Web Of Science, ORCID
Added: March 11, 2024

2023 journal article

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.

author keywords: Thorium dioxide; Post-irradiation annealing; Loop coarsening; Void growth; Cluster dynamics; Interstitials and vacancies
UN Sustainable Development Goal Categories
Sources: Web Of Science, ORCID
Added: October 16, 2023

2023 journal article

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.

author keywords: Direct energy deposition (DED); Additive manufacturing (AM); Austenitic 316L stainless steel; Irradiation-assisted stress corrosion cracking; (IASCC); Delta ferrite; Nanoindentation
Sources: Web Of Science, ORCID
Added: March 20, 2023

2023 journal article

STEM/EDS and APT study on the microstructure and microchemistry of neutron irradiated ZIRLOTM

Journal of Nuclear Materials, 573, 154139.

By: Z. Yu*, M. Bachhav*, F. Teng*, L. He*, M. Dubey* & A. Couet*

Sources: Crossref, ORCID
Added: June 26, 2023

2023 journal article

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.

By: X. Liu*, K. Bawane*, X. Zheng*, M. Ge*, P. Halstenberg*, D. Maltsev*, A. Ivanov*, S. Dai* ...

author keywords: dealloying; physical and chemical properties; molten chloride salt; Ni-based alloy; high-temperature corrosion
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, ORCID
Added: April 11, 2023

2023 journal article

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.

author keywords: Additive manufacturing; 316 L stainless steel; Hafnium; Directed energy deposition; High-throughput experimentation; Irradiation damage
Sources: Web Of Science, ORCID
Added: December 18, 2023

2023 journal article

Transmission electron microscopy investigation of phase transformation and fuel constituent redistribution in neutron irradiated U-10wt.%Zr fuel

JOURNAL OF NUCLEAR MATERIALS, 581.

author keywords: Transmission electron microscopy; Phase transformations; U-Zr; Nuclear fuel; Neutron irradiation
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, ORCID
Added: June 12, 2023

2023 journal article

Void swelling in additively manufactured 316L stainless steel with hafnium composition gradient under self-ion irradiation

Journal of Nuclear Materials, 578, 154351.

Sources: Crossref, ORCID
Added: July 2, 2023

2022 journal article

A combined theoretical-experimental investigation of thermal transport in low-dose irradiated thorium dioxide

Acta Materialia, 241, 118379.

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, ORCID
Added: June 26, 2023

2022 journal article

Assessing the interfacial corrosion mechanism of Inconel 617 in chloride molten salt corrosion using multi-modal advanced characterization techniques

Frontiers in Nuclear Engineering, 1.

Sources: Crossref, ORCID
Added: June 26, 2023

2022 journal article

Chemical and elemental mapping of spent nuclear fuel sections by soft X-ray spectromicroscopy

Journal of Synchrotron Radiation, 29(1), 67–79.

author keywords: spent nuclear fuel; STXM; oxygen K-edge; focused ion beam sections
TL;DR: Analysis of oxygen spectra using a modified non-negative matrix factorization method is consistent with a thin layer of hyperstoichiometric uranium oxide having been formed at the interface of a sample consisting of primarily UO2, probably formed after sample preparation. (via Semantic Scholar)
Source: ORCID
Added: December 5, 2022

2022 journal article

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.

author keywords: Direct energy deposition (DED) additively; manufacturing (AM); High-throughput alloy development; Radiation hardening; Irradiation-assisted stress corrosion cracking&nbsp; (IASCC); Stainless steel; Radiation-induced segregation
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Source: ORCID
Added: December 5, 2022

2022 journal article

Comprehensive characterization of irradiation induced defects in ceria: Impact of point defects on vibrational and optical properties

Journal of Applied Physics.

By: V. Chauhan*, J. Ferrigno*, S. Adnan*, J. Pakarinen*, L. He*, D. Hurley*, M. Khafizov*

Source: ORCID
Added: December 5, 2022

2022 journal article

Dislocation loop evolution in Kr‐irradiated ThO2

Journal of the American Ceramic Society.

author keywords: defects; dislocations; microstructure; oxides; transmission electron microscopy
Source: ORCID
Added: December 5, 2022

2022 journal article

Effect of dpa rate on the temperature regime of void swelling in ion-irradiated pure chromium

Journal of Nuclear Materials, 561, 153519.

By: A. Gabriel*, L. Hawkins*, A. French*, Y. Li*, Z. Hu*, L. He*, P. Xiu*, M. Nastasi*, F. Garner*, L. Shao*

UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Sources: Crossref, ORCID
Added: July 2, 2023

2022 journal article

Electrochemical noise studies on localized corrosion of Ni and Ni-20Cr in molten ZnCl2

Electrochimica Acta, 431, 141126.

Sources: Crossref, ORCID
Added: June 26, 2023

2022 journal article

In situ</i> TEM Observations of Thermally Activated Phenomena in Materials Under Far-From-Equilibrium Conditions

Microscopy and Microanalysis, 28(S1), 1844–1846.

By: S. Vijayan*, K. Bawane*, F. Giulia Dilemma*, L. He*, C. Fink* & J. Jinschek*

Sources: Crossref, ORCID
Added: July 2, 2023

2022 journal article

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.

By: Y. Wang*, X. Liu*, D. Murray*, F. Teng*, W. Jiang*, M. Bachhav*, L. Hawkins*, E. Perez* ...

Sources: Crossref, ORCID
Added: July 2, 2023

2022 journal article

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.

By: M. Pena*, A. Morell-Pacheco, C. Shiau, B. Kombaiah, L. He*, L. Hawkins, A. Gabriel, F. Garner, L. Shao

author keywords: Hastelloy N; Irradiation; Hardening; Pillar compression
Source: ORCID
Added: December 5, 2022

2022 journal article

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.

By: C. Parkin*, M. Moorehead*, M. Elbakhshwan*, X. Zhang*, P. Xiu*, L. He*, M. Bachhav*, K. Sridharan*, A. Couet*

Sources: Crossref, ORCID
Added: July 2, 2023

2022 journal article

Preparation and strengthening mechanism of prestressed ceramic tile components

International Journal of Applied Ceramic Technology.

By: Y. Sun*, T. Wu*, Y. Bao*, Y. Li*, D. Wan*, K. Li*, L. He*

author keywords: ceramic tiles; coating; flexural strength; pressureless sintering; prestressed components
Source: ORCID
Added: December 5, 2022

2022 journal article

Real-time, On-Microscope Automated Quantification of Features in Microcopy Experiments Using Machine Learning and Edge Computing

Microscopy and Microanalysis, 28(S1), 2046–2048.

By: K. Field*, P. Patki*, N. Sharaf, K. Sun*, L. Hawkins*, M. Lynch*, R. Jacobs*, D. Morgan*, L. He*, C. Field

TL;DR: Adoption of ML-based methods in various microscopy workflows has been restricted to only a few “super-user” groups due to the limited toolsets for performing distributed ML computing and difficulties with sharing software stacks that can be easily downloaded and run by any microscopist. (via Semantic Scholar)
Sources: Crossref, ORCID
Added: July 2, 2023

2022 journal article

Sensitization, desensitization, and carbide evolution of Alloy 800H made by laser powder bed fusion

Additive Manufacturing, 50, 102547.

author keywords: Alloy 800H; Laser powder bed fusion additive; manufacturing; Sensitization; Carbide formation; Dislocation cellular structures
Source: ORCID
Added: December 5, 2022

2022 journal article

Synthesis and characterization of uranium trichloride in alkali-metal chloride media

Journal of Nuclear Materials, 565, 153728.

By: S. Herrmann*, H. Zhao*, K. Bawane*, L. He*, K. Tolman* & X. Pu*

author keywords: Uranium trichloride synthesis; Uranium trichloride characterization; Uranium metal chlorination; Uranium hydride chlorination; Ammonium chloride
Source: ORCID
Added: December 5, 2022

2022 journal article

Thermal Energy Transport in Oxide Nuclear Fuel

Chemical Reviews.

By: D. Hurley*, A. El-Azab*, M. Bryan*, M. Cooper*, C. Dennett*, K. Gofryk*, L. He*, M. Khafizov* ...

TL;DR: A comprehensive review of thermal transport research on two actinide oxides: one currently in use in commercial nuclear reactors, uranium dioxide (UO2), and one advanced fuel candidate material, thorium dioxide (ThO2). (via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2022 journal article

Unraveling small-scale defects in irradiated ThO2 using kinetic Monte Carlo simulations

Scripta Materialia.

By: C. Jiang*, L. He*, C. Dennett, M. Khafizov*, J. Mann* & D. Hurley*

author keywords: Density functional theory (DFT); Monte Carlo simulation; Scanning; transmission electron microscopy; (STEM); Defects; Oxides
Source: ORCID
Added: December 5, 2022

2022 journal article

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.

By: K. Bawane*, X. Liu*, R. Gakhar*, M. Woods*, M. Ge*, X. Xiao*, W. Lee*, P. Halstenberg* ...

author keywords: Molten salt corrosion; quasi in situ TEM; dealloying; X-ray nano-tomography; in situ synchrotron
Source: ORCID
Added: December 5, 2022

2021 journal article

Advanced Characterization of Additively Manufactured 316L Stainless Steel for Nuclear Applications

Microscopy and Microanalysis, 27(S1), 2160–2161.

Sources: Crossref, ORCID
Added: June 20, 2023

2021 journal article

An integrated experimental and computational investigation of defect and microstructural effects on thermal transport in thorium dioxide

Acta Materialia, 213, 116934.

By: C. Dennett*, W. Deskins*, M. Khafizov*, Z. Hua*, A. Khanolkar*, K. Bawane*, L. Fu*, J. Mann* ...

author keywords: Thermal conductivity; Thorium dioxide; Defects; Boltzmann transport equation
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2021 journal article

Determining oxidation states of transition metals in molten salt corrosion using electron energy loss spectroscopy

Scripta Materialia, 197, 113790.

author keywords: Molten salt corrosion; Electron energy loss spectroscopy; Oxidation state mapping; Principal component analysis; Multiple linear least squares fitting
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2021 journal article

Dislocation Loops in Proton Irradiated Uranium-Nitrogen-Oxygen System

Journal of Nuclear Materials, 557, 153244.

By: P. Xiu*, M. Jin*, K. Bawane*, B. Tyburska-Püschel*, B. Jaques*, K. Field*, J. Giglio*, L. He*

author keywords: Radiation effects; Dislocation loops; Uranium nitride; Nuclear fuels
Source: ORCID
Added: December 5, 2022

2021 journal article

Early-stage microstructural evolution and phase stability in neutron-irradiated ferritic-martensitic steel T91

Journal of Nuclear Materials, 557, 153207.

author keywords: Ferritic/Martensitic (F/M) steel; Neutron irradiation; Dislocation loop; G phase; Irradiation hardening
Source: ORCID
Added: December 5, 2022

2021 journal article

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.

author keywords: Laser powder bed fusion additive manufacturing; Alloy 800H; Crack growth; Stress corrosion cracking; Corrosion fatigue; Sensitization
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Source: ORCID
Added: December 5, 2022

2021 journal article

First principle studies of effects of solute segregation on grain boundary strength in Ni-based alloys

Journal of Alloys and Compounds, 874, 159795.

By: Z. Xiao*, L. He* & X. Bai*

author keywords: Grain boundary strength; Radiation-induced segregation; Density functional theory; Nickel-based alloys
Source: ORCID
Added: December 5, 2022

2021 journal article

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.

author keywords: Fuel-cladding chemical interaction (FCCI); Metallic fuel; Advanced nuclear fuel; Transmission electron microscopy (TEM); HT-9 cladding; Phase transformation
Source: ORCID
Added: December 5, 2022

2021 journal article

In situ monitoring of microstructure evolution during thermal processing of uranium-zirconium alloys using laser-generated ultrasound

Journal of Nuclear Materials, 4, 153005.

Source: ORCID
Added: December 5, 2022

2021 journal article

Indirect characterization of point defects in proton irradiated ceria

Materialia, 15, 101019.

By: V. Chauhan*, J. Pakarinen*, T. Yao*, L. He*, D. Hurley* & M. Khafizov*

author keywords: Defect characterization; Microstructure evolution; Radiation damage
Source: ORCID
Added: December 5, 2022

2021 journal article

Investigating corrosion behavior of Ni and Ni-20Cr in molten ZnCl2

Corrosion Science, 179, 109105.

author keywords: Nickel-chromium; Molten chloride salts; Cyclic polarization; STEM/TEM; Intergranular corrosion
Source: ORCID
Added: December 5, 2022

2021 journal article

Isotopic Analysis of Irradiated Ceramic Fuel for Burnup and Microchemical Assessment Using Atom Probe Tomography.

Microscopy and Microanalysis, 27(S1), 416–417.

By: M. Bachhav*, J. Kane, F. Teng, F. Cappia & L. He*

Sources: Crossref, ORCID
Added: July 2, 2023

2021 journal article

Machine Learning Based Precision Orientation and Strain Mapping from 4D Diffraction Datasets

Microscopy and Microanalysis, 27(S1), 1276–1278.

By: R. Yuan*, J. Zhang*, L. He* & J. Zuo*

TL;DR: Four-dimensional diffraction datasets collected using the scanning electron nanodiffraction (SEND) or 4D scanning transmission electron microscopy (4D-STEM) techniques have gained increasing popularity in the electron microscopy community for their versatility in both electron diffraction and imaging. (via Semantic Scholar)
Sources: Crossref, ORCID
Added: June 20, 2023

2021 journal article

Metallic Fast Reactor Separate Effect Studies for Fuel Safety

Journal of Nuclear Engineering and Radiation Science, 7(4).

By: F. Lemma*, C. Jensen*, J. Kane*, W. Chen*, X. Liu*, L. Capriotti*, C. Adkins*, B. Kombaiah* ...

Source: ORCID
Added: December 5, 2022

2021 journal article

Nanoscale redistribution of alloying elements in high-burnup AXIOM-2 (X2®) and their effects on in-reactor corrosion

Corrosion Science, 190, 109652.

author keywords: APT; Zirconium; TEM; Microstructure; Irradiation; Corrosion
Source: ORCID
Added: December 5, 2022

2021 journal article

Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

Acta Materialia.

By: L. He*, M. Khafizov*, C. Jiang*, B. Tyburska-Püschel*, B. Jaques*, P. Xiu*, P. Xu*, M. Meyer* ...

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2021 journal article

Phase stability and microstructural evolution in neutron-irradiated ferritic-martensitic steel HT9

Journal of Nuclear Materials, 557, 153252.

author keywords: F/M steel; HT9; Neutron irradiation; Dislocation loop; Irradiation hardening
Source: ORCID
Added: December 5, 2022

2021 journal article

Proton irradiation-induced blistering in UO2

MRS Advances, 11.

By: J. Pakarinen*, L. He*, J. Gan*, A. Nelson*, A. El-Azab*, M. Khafizov*, T. Allen*

Source: ORCID
Added: December 5, 2022

2021 journal article

Structure of the pellet-cladding interaction layer of a high-burnup Zr-Nb-O nuclear fuel cladding

Journal of Nuclear Materials, 556, 153196.

author keywords: Neutron irradiation; Zr-nb-o alloy; Pellet-cladding interaction (pci); Interaction layer; Zirconium oxide; Transmission electron microscopy (tem); High-burnup fuel; post-irradiation examination (PIE)
Source: ORCID
Added: December 5, 2022

2021 journal article

TEM Characterization of Dislocation Loops in Proton Irradiated Single Crystal ThO2

Journal of Nuclear Materials, 4, 152998.

author keywords: Proton irradiation; defect analysis; dislocation loops; electron microscopy; thorium oxide; nuclear fuel
Source: ORCID
Added: December 5, 2022

2021 journal article

Thermal conductivity of ThO2: Effect of point defect disorder

Journal of Applied Physics.

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: February 1, 2024

2021 journal article

Training artificial neural networks for precision orientation and strain mapping using 4D electron diffraction datasets

Ultramicroscopy, 3, 113256.

By: R. Yuan*, J. Zhang*, L. He* & J. Zuo*

author keywords: Orientation mapping; Strain analysis; Scanning electron nanodiffraction; 4D-STEM; Artificial neural networks
MeSH headings : Electrons; Neural Networks, Computer
TL;DR: The ANN-enabled possibilities for the analysis of crystal orientation and strain at high precision are demonstrated and the performance of ANNs and CNNs is benchmarked by comparing with previous methods. (via Semantic Scholar)
Source: ORCID
Added: December 5, 2022

2021 journal article

Understanding spinodal and binodal phase transformations in U-50Zr

Materialia, 16, 101092.

By: T. Yao*, A. Sen*, A. Wagner*, F. Teng*, M. Bachhav*, A. EI-Azab*, D. Murray*, J. Gan* ...

Source: ORCID
Added: December 5, 2022

2020 journal article

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.

author keywords: Neutron irradiation; Stainless steel; Nickel-base alloys; Frank loops; Transmission electron microscopy (TEM); Superlattice reflection
Sources: ORCID, Crossref
Added: December 5, 2022

2020 journal article

Atom Probe Tomography for Burnup and Fission Product Analysis for Nuclear Fuels

Microscopy and Microanalysis, 26(S2), 3086–3088.

By: M. Bachhav*, L. He*, J. Kane*, X. Liu*, J. Gan* & F. Vurpiliot*

Sources: Crossref, ORCID
Added: June 20, 2023

2020 journal article

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.

By: M. Khafizov*, M. Riyad*, Y. Wang*, J. Pakarinen*, L. He*, T. Yao*, A. El-Azab*, D. Hurley*

author keywords: Point defects; Radiation damage; Uranium dioxide; Thermal conductivity; Thermoreflectance
Source: ORCID
Added: December 5, 2022

2020 journal article

Degradation mechanism of lead-vanado-iodoapatite in NaCl solution

Corrosion Science, 172, 108720.

author keywords: Lead-vanado-iodoapatite (IAPT); Degradation; Coupled interface dissolution-reprecipitation; Ion-exchange; Interface; STEM characterization
Sources: ORCID, Crossref
Added: December 5, 2022

2020 journal article

Development of a grain growth model for U3Si2 using experimental data, phase field simulation and molecular dynamics

Journal of Nuclear Materials, 532, 152069.

author keywords: U3Si2; Grain growth; Isothermal annealing experiments; Phase field; Grain boundary mobility
Sources: ORCID, Crossref, Web Of Science
Added: April 27, 2020

2020 journal article

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.

By: Y. Zhang*, Y. Lin*, L. He*, V. Murugesan*, G. Pawar*, B. Sivakumar*, H. Ding*, D. Ding* ...

author keywords: lithium-sulfur batteries; lean electrolytes; nickel sulfide; core-shell nanoparticles; electrolyte wetting
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: ORCID, Crossref
Added: December 5, 2022

2020 journal article

Effect of proton pre-irradiation on corrosion of Zr-0.5Nb model alloys with different Nb distributions

Corrosion Science, 173, 108790.

author keywords: Irradiation effect; Zirconium alloys; Nuclear fuel cladding; Corrosion kinetics; TEM; APT; EDS; Accelerated corrosion; Corrosion breakway
Sources: ORCID, Crossref
Added: December 5, 2022

2020 journal article

Electron microscopy characterization of fast reactor MOX Joint Oxyde-Gaine (JOG)

Journal of Nuclear Materials, 531, 151964.

By: F. Cappia*, B. Miller*, J. Aguiar*, L. He*, D. Murray*, B. Frickey*, J. Stanek*, J. Harp*

author keywords: SFR; MOX; JOG; Electron microscopy; PIE; Cs2MoO4
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Sources: ORCID, Crossref
Added: December 5, 2022

2020 journal article

Enhanced Resistance to Irradiation Induced Ferritic Transformation in Nanostructured Austenitic Steels

Materialia.

author keywords: Austenitic Steels; Irradiation Induced Phase Transformation; Nanostructured Materials; Severe Plastic Deformation; Irradiation Induced Segregation; Irradiation Induced Precipitation
Source: ORCID
Added: December 5, 2022

2020 journal article

Experimental evidence for ‘buckle, ruck and tuck’ in neutron irradiated graphite

Carbon, 159, 119–121.

By: S. Johns*, L. He*, J. Kane*, W. Windes*, R. Ubic* & C. Karthik*

Source: ORCID
Added: December 5, 2022

2020 journal article

Fullerene-like defects in high-temperature neutron-irradiated nuclear graphite

Carbon, 166, 113–122.

Sources: ORCID, Crossref
Added: December 5, 2022

2020 journal article

Impact of krypton irradiation on a single crystal tungsten: Multi-modal X-ray imaging study

Scripta Materialia, 188, 296–301.

By: S. Gill*, M. Topsakal*, E. Jossou*, X. Huang*, K. Hattar*, J. Mausz*, M. Elbakhshwan*, H. Yan* ...

author keywords: Strain mapping; Ion irradiation; Microstructure; Synchrotron radiation; Scanning transmission electron microscopy (STEM)
Sources: ORCID, Crossref
Added: December 5, 2022

2020 journal article

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.

By: C. Parkin*, M. Moorehead*, M. Elbakhshwan*, J. Hu*, W. Chen*, M. Li*, L. He*, K. Sridharan*, A. Couet*

author keywords: Irradiation effect; Ion irradiation; In situ transmission electron microscopy; Complex concentrated solid-solution alloy; Cryogenic temperature
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: ORCID, Crossref
Added: December 5, 2022

2020 journal article

Intragranular thermal transport in U–50Zr

Journal of Nuclear Materials, 534, 152145.

author keywords: Intragranular thermal conductivity; U-50Zr
Sources: ORCID, Crossref
Added: December 5, 2022

2020 journal article

On spinodal-like phase decomposition in U–50Zr alloy

Materialia.

author keywords: Spinodal; Phase decomposition; Ion irradiation; Alloy
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2020 journal article

Revealing 3D Morphological and Chemical Evolution Mechanisms of Metals in Molten Salt by Multimodal Microscopy

ACS Applied Materials & Interfaces, 12(15), 17321–17333.

author keywords: chloride molten salt; high-temperature corrosion; Ni-based alloys; X-ray CT; TXM; molten salt corrosion; dealloying; multiscale imaging
TL;DR: This work elucidates better mechanistic understanding of corrosion in molten salts, which can contribute to the design of more reliable alloys for molten salt applications including next-generation nuclear and solar power plants and opens the possibility of using molten salts to fabricate functional porous materials. (via Semantic Scholar)
Source: ORCID
Added: December 5, 2022

2020 article proceedings

TEM and APT Characterization of Neutron Irradiated AXIOM-2(X2)

Presented at the 2020 ANS Virtual Winter Meeting.

By: A. Couet, L. He*, M. Bachhav & Z. Yu

Event: 2020 ANS Virtual Winter Meeting

Sources: Crossref, ORCID
Added: June 26, 2023

2020 journal article

The correlation between microstructure and nanoindentation property of neutron-irradiated austenitic alloy D9

Acta Materialia, 195, 433–445.

author keywords: Microstructure-property relationship; Microstructural evolution under irradiation; Radiation hardening; Nanoindentation creep; Irradiation embrittlement
Source: ORCID
Added: December 5, 2022

2020 journal article

The influence of lattice defects, recombination, and clustering on thermal transport in single crystal thorium dioxide

APL Materials.

By: C. Dennett*, Z. Hua*, A. Khanolkar*, T. Yao*, P. Morgan*, T. Prusnick*, N. Poudel*, A. French* ...

Source: ORCID
Added: December 5, 2022

2020 journal article

α-U and ω-UZr2 in neutron irradiated U-10Zr annular metallic fuel

Journal of Nuclear Materials, 542, 152536.

By: T. Yao*, L. Capriotti*, J. Harp*, X. Liu*, Y. Wang*, F. Teng*, D. Murray*, A. Winston* ...

author keywords: Metallic fuel; Swelling; Microstructure; Spinodal decomposition; Radiation damage; Annular fuel
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2019 journal article

A simple way to make pre-stressed ceramics with high strength

Journal of Materiomics, 5(4), 657–662.

author keywords: Pre-stressed ceramics; Coating; Strength; Thermal shock resistance
Sources: ORCID, Crossref
Added: December 5, 2022

2019 journal article

Characterization of U-Pu-Zr alloys with Pd as a minor additive

Transactions of the American Nuclear Society, 120.

By: M. Benson, Y. Xie, L. He & J. King

Source: NC State University Libraries
Added: July 22, 2023

2019 journal article

Diffusion Behavior between Metallic Fuel Alloys with Pd Addition and Fe

Journal of Nuclear Materials, 525, 111–124.

author keywords: Fuel-cladding chemical interaction; Fuel additive; Diffusion; Metallic fuel
Sources: ORCID, NC State University Libraries
Added: December 5, 2022

2019 journal article

Diffusion behaviors between Fe and Pd-containing metallic fuel

Transactions of the American Nuclear Society, 120(1), 412–413.

By: Y. Xie, M. Benson, L. He & J. King

Source: NC State University Libraries
Added: July 22, 2023

2019 journal article

Impact of irradiation induced dislocation loops on thermal conductivity in ceramics

Journal of the American Ceramic Society, 102(12), 7533–7542.

By: M. Khafizov*, J. Pakarinen*, L. He* & D. Hurley*

author keywords: dislocation loops; radiation damage; thermal conductivity
Source: ORCID
Added: December 5, 2022

2019 report

Irradiation Testing Strategy for Commercialization of a Molten Chloride Fast Reactor System

By: A. Palmer, M. Holbrook, A. Jaoude, G. Core, G. Cao, K. Marsden, L. He, S. Frank, P. Calderoni

Source: NC State University Libraries
Added: July 22, 2023

2019 journal article

Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln

Journal of Nuclear Materials, 518, 287–297.

author keywords: Metallic fuel; FCCI; Fuel additive; Transmutation fuel
Source: ORCID
Added: December 5, 2022

2019 journal article

Microstructure and microchemistry study of irradiation-induced precipitates in proton irradiated ZrNb alloys

Acta Materialia.

author keywords: Irradiation; Microstructure; ZrNb
Source: ORCID
Added: December 5, 2022

2019 journal article

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.

By: S. Nguyen*, T. Nakayama*, H. Suematsu*, H. Iwasawa*, T. Suzuki*, Y. Otsuka*, L. He*, T. Takahashi*, K. Niihara*

author keywords: Crack-healing; Silicon carbide; Ceramic; Ytterbium silicate; Nanofiller
Sources: ORCID, Crossref
Added: December 5, 2022

2019 conference paper

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.

By: L. He, D. Murray, X. Liu, W. Jiang, M. Bachhav, X. Bai, S. Teysseyre

Event: 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors at Boston, MA on August 11-15, 2019

Source: NC State University Libraries
Added: July 22, 2023

2018 journal article

Challenges and Opportunities on Elucidating Irradiated Fuels with Atom Probe Tomography

Microscopy and Microanalysis, 24(S1), 2206–2207.

By: M. Bachhav*, J. Gan*, L. He*, B. Miller* & D. Keiser*

Sources: ORCID, Crossref
Added: December 5, 2022

2018 journal article

Evaluation of U3Si2 Fuel Pellets Sintered in an Argon vs. Vacuum Environment

Ceramic Transactions Series, 10, 21–26.

By: R. Hoggan*, J. Harp* & L. He*

Sources: ORCID, Crossref
Added: December 5, 2022

2018 journal article

Formation of tetragonal gas bubble superlattice in bulk molybdenum under helium ion implantation

Scripta Materialia.

Lingfeng He

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2018 journal article

Formation of tetragonal gas bubble superlattice in bulk molybdenum under helium ion implantation

Scripta Materialia, 149, 26–30.

By: C. Sun*, D. Sprouster*, K. Hattar*, L. Ecker*, L. He*, Y. Gao*, Y. Zhang*, J. Gan*

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, ORCID
Added: July 2, 2023

2018 journal article

Hydrothermal synthesis of silicon oxide clad uranium oxide nanowires

Journal of the American Ceramic Society.

By: L. He*, J. Harp*, A. Wagner*, R. Hoggan* & K. Tolman*

author keywords: hydrothermal; nanomaterials; nanowires; oxides; uranium; uranium compounds
Source: ORCID
Added: December 5, 2022

2018 journal article

In-situ TEM study of the ion irradiation behavior of U3Si2 and U3Si5

Journal of Nuclear Materials, 511, 56–63.

UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Source: ORCID
Added: December 5, 2022

2018 journal article

Interdiffusion behavior of U3Si2 with FeCrAl via diffusion couple studies

Journal of Nuclear Materials, 502, 356–369.

By: R. Hoggan*, L. He* & J. Harp*

author keywords: U3Si2; FeCrAl; Cladding
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Source: ORCID
Added: December 5, 2022

2018 journal article

Investigating Pd as a Potential Fuel Additive in a Transmutation Fuel to Control FCCI

Transactions of the American Nuclear Society, 118, 1379–1380.

By: M. Benson, L. He, J. King & R. Mariani

Source: NC State University Libraries
Added: July 22, 2023

2018 journal article

Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive

Journal of Nuclear Materials.

author keywords: FCCI; Metallic fuel; Fuel additive
Source: ORCID
Added: December 5, 2022

2018 journal article

Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln

Journal of Nuclear Materials, 508, 310–318.

By: M. Benson*, L. He*, J. King*, R. Mariani*, A. Winston* & J. Madden*

author keywords: Metallic fuel; FCCI; Fuel additive; Transmutation fuel
Source: ORCID
Added: December 5, 2022

2018 journal article

Radiation-induced grain subdivision and bubble formation in U3Si2 at LWR temperature

Journal of Nuclear Materials, 498, 169–175.

author keywords: U3Si2 fuel; Ion irradiation; Gas bubble; Polygonization; Oxidation
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Source: ORCID
Added: December 5, 2022

2018 journal article

STEM-EDS/EELS and APT characterization of ZrN coatings on UMo fuel kernels

Journal of Nuclear Materials, 511, 174–182.

By: L. He*, M. Bachhav*, D. Keiser*, J. Madden*, E. Perez*, B. Miller*, J. Gan*, W. Renterghem*, A. Leenaers*, S. Berghe*

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2018 journal article

Thermal stability of helium bubble superlattice in Mo under TEM in-situ heating

Journal of Nuclear Materials, 505, 207–211.

By: J. Gan, C. Sun, L. He*, Y. Zhang*, C. Jiang* & Y. Gao*

author keywords: Helium; Ion irradiation; Gas bubble superlattice; Transmission electron microscopy; In-situ heating
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2017 journal article

Bubble evolution in Kr-irradiated UO2 during annealing

Journal of Nuclear Materials, 496, 242–250.

By: L. He*, X. Bai*, J. Pakarinen*, B. Jaques*, J. Gan*, A. Nelson*, A. El-Azab*, T. Allen*

Source: ORCID
Added: December 5, 2022

2017 journal article

Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121–1085°C temperature range

Journal of Nuclear Materials.

Lingfeng He

Source: ORCID
Added: December 5, 2022

2017 chapter

Interdiffusion Behavior of FeCrAl with U3Si2

In J. Jackson, D. Paraventi, & M. Wright (Eds.), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (pp. 1391–1400).

By: R. Hoggan*, L. He* & J. Harp*

Ed(s): J. Jackson, D. Paraventi & M. Wright

Sources: Crossref, ORCID
Added: July 2, 2023

2017 journal article

Interdiffusion Behavior of U3Si2 and FeCrAl via Diffusion Couple Studies

Transactions of the American Nuclear Society, 116, 403–406.

By: R. Hoggan, J. Harp & L. He

Source: NC State University Libraries
Added: July 22, 2023

2017 chapter book

Irradiation effects in Generation IV nuclear reactor materials

By: A. Aitkaliyeva*, L. He*, H. Wen*, B. Miller*, X. Bai* & T. Allen*

UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Sources: Crossref, ORCID
Added: June 26, 2023

2017 journal article

Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C

Journal of Nuclear Materials, 486, 274–282.

By: L. He*, J. Harp*, R. Hoggan* & A. Wagner*

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2017 journal article

Strength improvement and purification of Yb<sub>2 Si<sub>2 O<sub>7 -SiC nanocomposites by surface oxidation treatment

Journal of the American Ceramic Society, 100(7), 3122–3131.

By: S. Nguyen*, T. Nakayama*, H. Suematsu*, T. Suzuki*, L. He*, H. Cho*, K. Niihara*

author keywords: cracks; cracking; nanocomposites; oxidation; silicon carbide; strength
Sources: ORCID, Crossref
Added: December 5, 2022

2016 journal article

Corrosion-induced microstructural developments in 316 stainless steel during exposure to molten Li2BeF4 (FLiBe) salt

Journal of Nuclear Materials, 482, 147–155.

By: G. Zheng*, L. He*, D. Carpenter* & K. Sridharan*

Contributors: G. Zheng*, L. He*, D. Carpenter* & K. Sridharan*

author keywords: Nuclear reactor; 316 stainless steel; Molten salt; Microstructure; Corrosion
Source: ORCID
Added: December 5, 2022

2016 journal article

Effect of neutron irradiation on defect evolution in Ti3SiC2 and Ti2AlC

Journal of Nuclear Materials, 468, 194–206.

By: D. Tallman*, L. He*, B. Garcia-Diaz*, E. Hoffman*, G. Kohse*, R. Sindelar*, M. Barsoum*

Contributors: D. Tallman*, L. He*, B. Garcia-Diaz*, E. Hoffman*, G. Kohse*, R. Sindelar*, M. Barsoum*

author keywords: Ti3SiC2; Ti2AlC; MAX phases; Neutron irradiation; Dislocation loops
Source: ORCID
Added: December 5, 2022

2016 chapter

Irradiation Effects in Generation IV Nuclear Reactor Materials

Lingfeng He

UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Source: ORCID
Added: December 5, 2022

2016 journal article

MAX Phases for the Nuclear Industry: Possibilities and Pitfalls

Transactions of the American Nuclear Society, 114, 1242–1243.

By: M. Barsoum, D. Tallman, L. He & J. Gan

Source: NC State University Libraries
Added: July 22, 2023

2016 journal article

Microstructure Evolution in Ion-Irradiated UO2

Transactions of the American Nuclear Society, 114, 1130–1131.

By: L. He, J. Gan & T. Allen

Source: NC State University Libraries
Added: July 22, 2023

2016 journal article

Subsurface imaging of grain microstructure using picosecond ultrasonics

Acta Materialia, 112, 209–215.

Contributors: M. Khafizov*, J. Pakarinen*, L. He*, H. Henderson*, M. Manuel*, A. Nelson*, B. Jaques*, D. Butt*, D. Hurley*

author keywords: Picosecond ultrasonics; Grain orientation; Boundary characterization
Source: ORCID
Added: December 5, 2022

2015 journal article

Annealing-induced lattice recovery in room-temperature xenon irradiated CeO2: X-ray diffraction and electron energy loss spectroscopy experiments

Journal of Materials Research, 30(9), 1555–1562.

By: J. Pakarinen*, L. He*, A. Hassan*, Y. Wang*, M. Gupta*, A. El-Azab*, T. Allen*

Contributors: J. Pakarinen*, L. He*, A. Hassan*, Y. Wang*, M. Gupta*, A. El-Azab*, T. Allen*

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2015 journal article

Bubble formation and Kr distribution in Kr-irradiated UO2

Journal of Nuclear Materials, 456, 125–132.

By: L. He*, B. Valderrama*, A. Hassan*, J. Yu*, M. Gupta*, J. Pakarinen*, H. Henderson*, J. Gan* ...

Contributors: L. He*, B. Valderrama*, A. Hassan*, J. Yu*, M. Gupta*, J. Pakarinen*, H. Henderson*, J. Gan* ...

Source: ORCID
Added: December 5, 2022

2015 journal article

High-Temperature corrosion of UNS N10003 in Molten Li2BeF4 (FLiBe) Salt

Corrosion, 71(10), 1257–1266.

By: G. Zheng, B. Kelleher*, L. He*, G. Cao, M. Anderson, T. Allen, K. Sridharan

Contributors: G. Zheng, B. Kelleher*, L. He*, G. Cao, M. Anderson, T. Allen, K. Sridharan

author keywords: corrosion; FLiBe; Hastelloy N; molten salt; nuclear reactor; UNS N10003
Source: ORCID
Added: December 5, 2022

2015 journal article

Inert Gas Measurement of Single Bubble in CeO2

Microsc. Microanal.

Lingfeng He

Source: ORCID
Added: December 5, 2022

2015 journal article

Inert Gas Measurement of Single Bubble in CeO2

Microscopy and Microanalysis, 21(S3), 751–752.

By: L. He*, J. Pakarinen*, X. Bai*, J. Gan*, Y. Wang*, A. El-Azab*, T. Allen*

Sources: Crossref, ORCID
Added: June 26, 2023

2014 journal article

2.6 MeV proton irradiation effects on the surface integrity of depleted UO2

Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 319, 100–106.

By: J. Pakarinen*, L. He*, M. Gupta*, J. Gan*, A. Nelson*, A. El-Azab*, T. Allen*

Contributors: J. Pakarinen*, L. He*, M. Gupta*, J. Gan*, A. Nelson*, A. El-Azab*, T. Allen*

author keywords: Uranium dioxide; Proton irradiation; Surface flaking; Crystal damage
Source: ORCID
Added: December 5, 2022

2014 journal article

Corrosion behavior of an alumina forming austenitic steel exposed to supercritical carbon dioxide

Corrosion Science, 82, 67–76.

By: L. He*, P. Roman*, B. Leng*, K. Sridharan*, M. Anderson* & T. Allen*

Contributors: L. He*, P. Roman*, B. Leng*, K. Sridharan*, M. Anderson* & T. Allen*

author keywords: Stainless steels; SEM; STEM; High temperature corrosion; Oxidation; Carburization
Source: ORCID
Added: December 5, 2022

2014 book

Developing yttria-based ceramics having high liquid metal corrosion resistance

In Ceramic Transactions (Vol. 250, pp. 53–63). http://www.scopus.com/inward/record.url?eid=2-s2.0-84908214876&partnerID=MN8TOARS

By: S. Nguyen, T. Nakayama, S. Rozali, H. Suematsu, T. Suzuki, W. Jiang, S. Amarume, L. He, K. Niihara

Contributors: S. Nguyen, T. Nakayama, S. Rozali, H. Suematsu, T. Suzuki, W. Jiang, S. Amarume, L. He, K. Niihara

Source: ORCID
Added: December 5, 2022

2014 journal article

Effect of Grain Boundaries on Krypton Segregation Behavior in Irradiated Uranium Dioxide

JOM, 66(12), 2562–2568.

Contributors: B. Valderrama*, L. He*, H. Henderson*, J. Pakarinen*, B. Jaques*, J. Gan*, D. Butt*, T. Allen*, M. Manuel*

Source: ORCID
Added: December 5, 2022

2014 journal article

In Situ TEM Observation of Dislocation Evolution in Polycrystalline UO2

JOM, 66(12), 2553–2561.

By: L. He*, M. Gupta*, M. Kirk*, J. Pakarinen*, J. Gan* & T. Allen*

Contributors: L. He*, M. Gupta*, M. Kirk*, J. Pakarinen*, J. Gan* & T. Allen*

Source: ORCID
Added: December 5, 2022

2014 journal article

Microstructure changes and thermal conductivity reduction in UO2 following 3.9 MeV He2+ ion irradiation

Journal of Nuclear Materials, 454(1-3), 283–289.

By: J. Pakarinen*, M. Khafizov*, L. He*, C. Wetteland*, J. Gan*, A. Nelson*, D. Hurley*, A. El-Azab*, T. Allen*

Contributors: J. Pakarinen*, M. Khafizov*, L. He*, C. Wetteland*, J. Gan*, A. Nelson*, D. Hurley*, A. El-Azab*, T. Allen*

Sources: ORCID, Crossref
Added: December 5, 2022

2014 journal article

Microstructure evolution in Xe-irradiated UO2 at room temperature

Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 330, 55–60.

By: L. He*, J. Pakarinen*, M. Kirk*, J. Gan*, A. Nelson*, X. Bai*, A. El-Azab*, T. Allen*

Contributors: L. He*, J. Pakarinen*, M. Kirk*, J. Gan*, A. Nelson*, X. Bai*, A. El-Azab*, T. Allen*

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2014 journal article

Synthesis of BN nanosheet/nanotube-Fe nanocomposites by pulsed wire discharge and high-temperature annealing

Materials Letters, 117, 120–123.

By: L. He*, J. Shirahata, H. Suematsu, T. Nakayama, T. Suzuki, W. Jiang, K. Niihara

Contributors: L. He*, J. Shirahata, H. Suematsu, T. Nakayama, T. Suzuki, W. Jiang, K. Niihara

author keywords: Boron nitride; Fe nanoparticles; Nanocomposites; Pulsed wire discharge; Catalyst
Source: ORCID
Added: December 5, 2022

2014 journal article

Thermal conductivity in nanocrystalline ceria thin films

Journal of the American Ceramic Society, 97(2), 562–569.

By: M. Khafizov*, I. Park*, A. Chernatynskiy*, L. He*, J. Lin*, J. Moore*, D. Swank*, T. Lillo* ...

Contributors: M. Khafizov*, I. Park*, A. Chernatynskiy*, L. He*, J. Lin*, J. Moore*, D. Swank*, T. Lillo* ...

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2013 conference paper

Characterization of Oxide Films on Alloys 600 and 690 Exposed to Supercritical and Subcritical Water

16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Presented at the 16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Asheville, NC.

By: L. He, G. Cao, K. Sridharan, T. Allen, T. Moss, G. Was, T. Lian

Event: 16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors at Asheville, NC on August 11-15, 2013

Source: NC State University Libraries
Added: July 22, 2023

2013 journal article

Fission Products in Nuclear Fuel: Comparison of Simulated Distribution with Correlative Characterization Techniques

Lingfeng He

Source: ORCID
Added: December 5, 2022

2013 journal article

Fission Products in Nuclear Fuel: Comparison of Simulated Distribution with Correlative Characterization Techniques

Microscopy and Microanalysis, 19(S2), 968–969.

By: B. Valderrama, H. Henderson, L. He*, C. Yablinsky, J. Gan, A. Hassan, A. El-Azab, T. Allen, M. Manuel

Sources: Crossref, ORCID
Added: June 26, 2023

2013 journal article

In situ TEM observation of dislocation evolution in Kr-irradiated UO 2 single crystal

Journal of Nuclear Materials, 443(1-3), 71–77.

By: L. He*, M. Gupta*, C. Yablinsky*, J. Gan*, M. Kirk*, X. Bai*, J. Pakarinen*, T. Allen*

Contributors: T. Allen*, X. Bai*, J. Gan*, M. Gupta*, L. He*, M. Kirk*, J. Pakarinen*, C. Yablinsky*

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2013 journal article

Synthesis and structure-property relationships of a new family of layered carbides in Zr-Al(Si)-C and Hf-Al(Si)-C systems

Journal of the European Ceramic Society.

By: Y. Zhou*, L. He*, Z. Lin* & J. Wang*

Contributors: L. He*, Z. Lin*, J. Wang* & Y. Zhou*

author keywords: Layered carbides; Crystal structure; Processing; Structure-property relationships
Source: ORCID
Added: December 5, 2022

2013 journal article

Transmission electron microscopy investigation of krypton bubbles in polycrystalline CeO2

Nuclear Technology, 182(2), 164–169. http://www.scopus.com/inward/record.url?eid=2-s2.0-84879071544&partnerID=MN8TOARS

By: L. He, C. Yablinsky, M. Gupta, J. Gan, M. Kirk & T. Allen

Contributors: L. He, C. Yablinsky, M. Gupta, J. Gan, M. Kirk & T. Allen

Source: ORCID
Added: December 5, 2022

2011 journal article

Effect of Ti dopant on the mechanical properties and oxidation behavior of Zr 2[Al(Si)] 4C 5 ceramics

Journal of the American Ceramic Society, 94(6), 1872–1877.

By: X. Lu*, H. Xiang*, L. He*, L. Sun* & Y. Zhou*

Contributors: L. He*, X. Lu*, L. Sun*, H. Xiang* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

2011 journal article

Fabrication and characterization of tricalcium silicate bioceramics with high mechanical properties by spark plasma sintering

International Journal of Applied Ceramic Technology, 8(3), 501–510.

TL;DR: Ca3SiO5 ceramics fabricated by SPS possess excellent mechanical properties, bioactivity, and biocompatibility and are promising bone repaired materials. (via Semantic Scholar)
Source: ORCID
Added: December 5, 2022

2011 journal article

Mechanical properties and bioactivity of β-Ca 2SiO 4 ceramics synthesized by spark plasma sintering

Ceramics International, 37(7), 2459–2465.

Contributors: J. Chang*, L. Chen*, Y. Fan*, L. He*, W. Jiang*, K. Lin*, L. Wang*, H. Zhong*

author keywords: Beta-dicalium silicate ceramics; Mechanical properties; Bioactivity; Spark plasma sintering
Source: ORCID
Added: December 5, 2022

2011 journal article

Mechanical properties of Y2Ti2O7

Scripta Materialia, 64(6), 548–551.

By: L. He*, J. Shirahata*, T. Nakayama*, T. Suzuki*, H. Suematsu*, I. Ihara*, Y. Bao*, T. Komatsu*, K. Niihara*

Contributors: Y. Bao*, L. He*, I. Ihara*, T. Komatsu*, T. Nakayama*, K. Niihara*, J. Shirahata*, H. Suematsu*, T. Suzuki*

author keywords: Y2Ti2O7; Mechanical properties; Hardness; Elastic behavior; Nanoindentation
Source: ORCID
Added: December 5, 2022

2010 journal article

A new method to improve the high-temperature mechanical properties of Ti3SiC2 by substituting Ti with Zr, Hf, or Nb

Journal of the American Ceramic Society, 93(6), 1749–1753.

Source: ORCID
Added: December 5, 2022

2010 journal article

Crystal structure and theoretical elastic property of a new ternary ceramic HfAl4C4

Journal of the American Ceramic Society, 93(4), 1164–1168.

By: H. Nian*, L. He*, F. Li*, J. Wang* & Y. Zhou*

Contributors: L. He*, F. Li*, H. Nian*, J. Wang* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

2010 journal article

In situ reaction synthesis and mechanical properties of TaC-TaSi 2 composites

International Journal of Applied Ceramic Technology, 7(6), 697–703.

By: C. Hu*, L. He*, F. Li*, L. Wu*, J. Wang*, M. Li*, Y. Bao*, Y. Zhou*

Contributors: Y. Bao*, L. He*, C. Hu*, F. Li*, M. Li*, J. Wang*, L. Wu*, Y. Zhou*

Source: ORCID
Added: December 5, 2022

2010 journal article

Mechanical and thermal properties of a Hf2[Al(Si)]4C5 ceramic prepared by in situ reaction/hot-pressing

Scripta Materialia, 62(6), 427–430.

By: L. He*, H. Nian*, X. Lu*, Y. Bao* & Y. Zhou*

Contributors: Y. Bao*, L. He*, X. Lu*, H. Nian* & Y. Zhou*

author keywords: Carbides; Hot-pressing; High temperature; Mechanical property; Thermal property
Source: ORCID
Added: December 5, 2022

2010 journal article

Mechanisms and kinetics of the hydrothermal oxidation of bulk titanium silicon carbide

Journal of the American Ceramic Society, 93(4), 1148–1155.

By: H. Zhang*, V. Presser*, C. Berthold*, K. Nickel*, X. Wang*, C. Raisch*, T. Chassé*, L. He*, Y. Zhou*

Contributors: C. Berthold*, T. Chassé*, L. He*, K. Nickel*, V. Presser*, C. Raisch*, X. Wang*, H. Zhang*, Y. Zhou*

UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Source: ORCID
Added: December 5, 2022

2010 journal article

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.

By: L. He*, F. Li*, X. Lu*, Y. Bao* & Y. Zhou*

Contributors: Y. Bao*, L. He*, F. Li*, X. Lu* & Y. Zhou*

author keywords: Carbides; Microstructure; Mechanical properties; Thermal properties; Corrosion
Source: ORCID
Added: December 5, 2022

2010 journal article

Oxidation behavior of ternary carbide ceramics in Hf-Al-C system in air

Journal of the American Ceramic Society, 93(10), 3427–3431.

By: L. He*, J. Li*, H. Nian*, X. Wang*, Y. Bao*, M. Li*, J. Wang*, Y. Zhou*

Contributors: Y. Bao*, L. He*, J. Li*, M. Li*, H. Nian*, J. Wang*, X. Wang*, Y. Zhou*

Source: ORCID
Added: December 5, 2022

2010 journal article

Reciprocating friction and wear behavior of Zr2[Al(Si)] 4C5 and Zr2[Al(Si)]4C 5-SiC composite against Si3N4 ball

Journal of the American Ceramic Society, 93(8), 2369–2376.

By: L. Wu*, L. He*, J. Chen*, X. Lu* & Y. Zhou*

Contributors: J. Chen*, L. He*, X. Lu*, L. Wu* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

2010 journal article

Surface strengthening of Ti3SiC2 through magnetron sputtering of Mo and Zr and subsequent annealing

Journal of the European Ceramic Society, 30(10), 2123–2130.

By: H. Guo*, A. Li*, J. Zhang*, L. He* & Y. Zhou*

Contributors: H. Guo*, L. He*, A. Li*, J. Zhang* & Y. Zhou*

author keywords: Ti3SiC2; Surface strengthening; Magnetron sputtering; Microhardness
Source: ORCID
Added: December 5, 2022

2009 journal article

High-temperature internal friction, stiffness and strength of Zr-Al(Si)-C ceramics

Scripta Materialia, 61(1), 60–63.

By: L. He*, X. Lu*, Y. Bao*, J. Wang* & Y. Zhou*

Contributors: Y. Bao*, L. He*, X. Lu*, J. Wang* & Y. Zhou*

author keywords: Carbide; TEM; Grain boundaries; Elastic behavior; Internal friction
Source: ORCID
Added: December 5, 2022

2009 journal article

Highly conductive and strengthened copper matrix composite reinforced by Zr2Al3C4 particulates

Scripta Materialia, 60(11), 976–979.

By: J. Zhang*, L. He* & Y. Zhou*

Contributors: L. He*, J. Zhang* & Y. Zhou*

author keywords: Cu/Zr2Al3C4 Composite; Electrical conductivity; Mechanical properties
Source: ORCID
Added: December 5, 2022

2009 journal article

Mechanical and thermophysical properties of Zr-Al-Si-C ceramics

Journal of the American Ceramic Society, 92(2), 445–451.

By: L. He*, Y. Bao*, J. Wang*, M. Li* & Y. Zhou*

Contributors: Y. Bao*, L. He*, M. Li*, J. Wang* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

2009 journal article

Microstructure and mechanical and thermal properties of ternary carbides in Hf-Al-C system

Acta Materialia, 57(9), 2765–2774.

By: L. He*, Y. Bao*, J. Wang*, M. Li* & Y. Zhou*

Contributors: Y. Bao*, L. He*, M. Li*, J. Wang* & Y. Zhou*

author keywords: Carbides; TEM; High temperature; Mechanical property; Thermal property
Source: ORCID
Added: December 5, 2022

2009 journal article

Tribological properties of a Zr2Al3C4 ceramic at ambient temperature

Journal of the American Ceramic Society, 92(1), 141–146.

By: L. Wu*, L. He*, Y. Bao* & Y. Zhou*

Contributors: Y. Bao*, L. He*, L. Wu* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

2009 journal article

Ultrahigh-temperature oxidation of Zr2Al3C4 via rapid induction heating

Scripta Materialia, 60(7), 547–550.

By: L. He*, H. Zhong, J. Xu, M. Li, Y. Bao, J. Wang, Y. Zhou

Contributors: Y. Bao, L. He*, M. Li, J. Wang, J. Xu, H. Zhong, Y. Zhou

author keywords: Zr2Al3C4; ZrO2; Al2O3; Oxidation; Induction heating
Source: ORCID
Added: December 5, 2022

2009 journal article

Zirconium aluminum carbides: New precursors for synthesizing ZrO 2-Al2O3 composites

Journal of the American Ceramic Society, 92(11), 2751–2758.

By: L. He*, Y. Bao* & Y. Zhou*

Contributors: Y. Bao*, L. He* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

2008 journal article

Atomic-scale microstructure and elastic properties of quaternary Zr-Al-Si-C ceramics

Acta Materialia, 56(9), 2022–2031.

By: Z. Lin*, L. He*, J. Wang*, M. Li*, Y. Bao* & Y. Zhou*

Contributors: Y. Bao*, L. He*, M. Li*, Z. Lin, J. Wang* & Y. Zhou*

author keywords: ceramics; hot-pressing; crystal structure; TEM; elastic property
Source: ORCID
Added: December 5, 2022

2008 journal article

Crystal structure and theoretical elastic property of two new ternary ceramics Hf3Al4C6 and Hf2Al4C5

Scripta Materialia, 58(8), 679–682.

Contributors: Y. Bao*, L. He*, Z. Lin*, J. Wang* & Y. Zhou*

author keywords: Hf3Al4C6; Hf2Al4C5; TEM; crystal structure; elastic properties
Source: ORCID
Added: December 5, 2022

2008 journal article

Improving the high-temperature oxidation resistance of Zr2 Al3C4 by silicon pack cementation

Journal of Materials Research, 23(8), 2275–2282.

Contributors: Y. Bao*, L. He*, M. Li*, J. Wang* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

2008 journal article

In Situ

Journal of the American Ceramic Society, 91(7), 2258–2263.

Sources: Crossref, ORCID
Added: June 26, 2023

2008 journal article

In situ reaction synthesis and mechanical properties of V2AlC

Journal of the American Ceramic Society, 91(12), 4029–4035.

By: C. Hu*, L. He*, M. Liu*, X. Wang*, J. Wang*, M. Li*, Y. Bao*, Y. Zhou*

Contributors: Y. Bao*, L. He*, C. Hu*, M. Li*, M. Liu, J. Wang*, X. Wang*, Y. Zhou*

Source: ORCID
Added: December 5, 2022

2008 journal article

Isothermal oxidation of bulk Zr2Al3C4 at 500 to 1000 °C in air

Journal of Materials Research, 23(2), 359–366.

Contributors: Y. Bao*, L. He*, M. Li*, Z. Lin, J. Wang* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

2008 journal article

Microstructure and properties of bulk Ta2AlC ceramic synthesized by an in situ reaction/hot pressing method

Journal of the European Ceramic Society, 28(8), 1679–1685.

By: C. Hu*, L. He*, J. Zhang*, Y. Bao*, J. Wang*, M. Li*, Y. Zhou*

Contributors: Y. Bao*, L. He*, C. Hu*, M. Li*, J. Wang*, J. Zhang*, Y. Zhou*

author keywords: Ta2AlC; hot pressing; electrical conductivity; thermal conductivity; mechanical properties
Source: ORCID
Added: December 5, 2022

2008 journal article

Oxidation of Zr<sub>2</sub>[Al(Si)]<sub>4</sub>C<sub>5</sub> and Zr<sub>3</sub>[Al(Si)]<sub>4</sub>C<sub>6</sub> in air

Journal of Materials Research, 23(12), 3339–3346.

Contributors: Y. Bao*, L. He*, M. Li*, J. Wang* & Y. Zhou*

Sources: ORCID, Crossref
Added: December 5, 2022

2008 journal article

Synthesis, Microstructure, and Mechanical Properties of Al3BC3

By: L. L.F. He

Source: ORCID
Added: December 5, 2022

2008 journal article

Synthesis, Microstructure, and Mechanical Properties of Al<sub>3

Journal of the American Ceramic Society, 91(7), 2343–2348.

Sources: Crossref, ORCID
Added: July 2, 2023

2007 journal article

Elastic and thermal properties of Zr2 Al3 C4: Experimental investigations and ab initio calculations

Journal of Applied Physics, 102(4).

By: L. He*, J. Wang*, Y. Bao* & Y. Zhou*

Contributors: Y. Bao*, L. He*, J. Wang* & Y. Zhou*

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Source: ORCID
Added: December 5, 2022

2007 journal article

In situ synthesis and properties of Ti 3AlC 2/TiB 2 composites

Journal of the American Ceramic Society, 90(11), 3615–3620.

By: C. Li*, M. Li*, Y. Zhou*, J. Zhang* & L. He*

Contributors: L. He*, C. Li*, M. Li*, J. Zhang* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

2007 journal article

Layered stacking characteristics of ternary zirconium aluminum carbides

Journal of Materials Research, 22(11), 3058–3066.

Contributors: L. He*, M. Li*, Z. Lin, J. Wang* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

2007 journal article

Physical and mechanical properties of bulk Ta4AlC3 ceramic prepared by an in situ reaction synthesis/hot-pressing method

Journal of the American Ceramic Society, 90(8), 2542–2548.

By: C. Hu*, Z. Lin*, L. He*, Y. Bao*, J. Wang*, M. Li*, Y. Zhou*

Contributors: Y. Bao*, L. He*, C. Hu*, M. Li*, Z. Lin, J. Wang*, Y. Zhou*

Source: ORCID
Added: December 5, 2022

2007 journal article

Synthesis and characterization of bulk Zr2Al3C 4 ceramic

Journal of the American Ceramic Society, 90(11), 3687–3689.

By: L. He*, Z. Lin*, J. Wang*, Y. Bao*, M. Li* & Y. Zhou*

Contributors: Y. Bao*, L. He*, M. Li*, Z. Lin, J. Wang* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

2007 journal article

Synthesis and oxidation of Zr3Al3C5 powders

International Journal of Materials Research, 98(1), 3–9. http://www.scopus.com/inward/record.url?eid=2-s2.0-33847074954&partnerID=MN8TOARS

By: L. He, Y. Zhou, Y. Bao, J. Wang & M. Li

Contributors: Y. Bao, L. He, M. Li, J. Wang & Y. Zhou

Source: ORCID
Added: December 5, 2022

2007 journal article

Synthesis and oxidation of Zr<inf>3</inf>Al<inf>3</inf>C<inf>5</inf> powders

International Journal of Materials Research, 98(1), 3–9. http://www.scopus.com/inward/record.url?eid=2-s2.0-33847074954&partnerID=MN8TOARS

By: L. He, Y. Zhou, Y. Bao, J. Wang & M. Li

Contributors: L. He, Y. Zhou, Y. Bao, J. Wang & M. Li

Source: ORCID
Added: December 5, 2022

2007 journal article

Synthesis, physical, and mechanical properties of bulk Zr 3Al3C5 ceramic

Journal of the American Ceramic Society, 90(4), 1164–1170.

Contributors: Y. Bao*, L. He*, Z. Lin*, J. Wang* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

2006 journal article

Atomic-scale microstructures of Zr2Al3C4 and Zr3Al3C5 ceramics

Acta Materialia, 54(14), 3843–3851.

By: Z. Lin*, M. Zhuo*, L. He*, Y. Zhou*, M. Li* & J. Wang*

Contributors: L. He*, M. Li*, Z. Lin, J. Wang*, Y. Zhou* & M. Zhuo*

author keywords: TEM; carbides; layered structures; STEM
Source: ORCID
Added: December 5, 2022

2006 journal article

First-principles prediction of the mechanical properties and electronic structure of ternary aluminum carbide Zr3 Al3 C5

Physical Review B - Condensed Matter and Materials Physics, 73(13).

Contributors: L. He*, T. Liao*, Z. Lin*, J. Wang* & Y. Zhou*

Source: ORCID
Added: December 5, 2022

conference paper

Corrosion and Interdiffusion Studies of U3Si2

Harp, J. M., He, L., Hoggan, R. E., & Wagner, A. R. Top Fuel 2016, 1341–1346.

By: J. Harp, L. He, R. Hoggan & A. Wagner

Event: Top Fuel 2016 at Boise, ID on September 11-16, 2016

Source: NC State University Libraries
Added: July 22, 2023

Employment

Updated: September 16th, 2022 08:50

2022 - present

North Carolina State University Raleigh, North Carolina, US
Associate Professor Nuclear Engineering

2017 - 2022

Idaho National Laboratory Idaho Falls, ID, US
TEM/HRMC Group Lead Advanced Characterization

2014 - 2022

Idaho National Laboratory Idaho Falls, ID, US
Staff Scientist/Senior Scientist/Distinguished Scientist Nuclear Fuels and Materials / Advanced Characterization

2011 - 2014

University of Wisconsin Madison Madison, WI, US
Postdoc Research Associate/Assistant Scientist Engineering Physics

2009 - 2011

Nagaoka Gijutsu Kagaku Daigaku Nagaoka, Niigata, JP
Fellow Researcher Extreme Energy-Density Research Institute

Education

Updated: January 5th, 2017 13:30

2003 - 2009

Chinese Academy of Sciences Beijing, CN
Ph.D.

1999 - 2003

Central South University Changsha, Hunan, CN
B. Eng Metallurgical Science and Engineering

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