"A transmission electron microscopy study of EBR-II neutron-irradiated austenitic stainless steel 304 and nickel-base alloy X-750"
Lingfeng He,
Journal of Nuclear Materials
Vol. 528
2020
1-9
Link
The microstructure of EBR-II neutron-irradiated austenitic stainless steel 304 and nickel-base alloy X-750 was investigated. Both alloys were irradiated at low dose rates (∼2 × 10−8 dpa/s) to a neutron fluence of 6.9 × 1022 n/cm2 (E > 0.1 MeV) at 371–389 °C. Different types of defects, including Frank loops, cavities, and precipitates were characterized. The Frank loops in Type 304 stainless steel (SS) are larger in size (∼50 nm in diameter) and lower in number density (2.58 × 1021 m−3), compared to most previous higher dose rate neutron irradiation studies. The Frank loops in X-750 have an average size 26.0 nm of and a number density of 9.44 × 1021 m−3. In 304 SS and X-750, cavities are of ∼20 nm and ∼14 nm in diameter, respectively. The swelling of both alloys was found to be insignificant. In 304 SS, Ni and Si were found enriched at the cavity surfaces and Ni,Si-rich precipitates were also found. Multivariate statistical analysis using non-negative matrix factorization reveals that these Ni,Si-rich precipitates contain only ∼5.7 at.% Si, differing from the Ni3Si precipitates found in several previous studies. In X-750, L12-structured precipitates were found, and multivariate statistical analysis confirmed the 3:1 stoichiometry (Ni3(Ti,Al)) of the precipitates and the superlattice reflections confirmed the stability of the crystal structure of these precipitates, indicating higher-than-expected precipitate stability under high-dose neutron irradiation. |
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"An integrated experimental and computational investigation of defect and microstructural effects on thermal transport in thorium dioxide" Marat Khafizov, Lingfeng He, Cody Dennett, David Hurley, Zilong Hua, Amey Khanolkar, Anter EL-AZAB, Kaustubh Bawane, Acta Materialia Vol. 213 2021 Link | ||
"Bubble Character, Kr Distribution and Chemical Equilibrium in UO2" Todd Allen, Anter EL-AZAB, Jian Gan, Mahima Gupta, Lingfeng He, Hunter Henderson, Michele Manuel, Andrew Nelson, Janne Pakarinen, Billy Valderrama, Journal of Nuclear Materials Vol. 2015 Link | ||
"Bubble evolution in Kr-irradiated UO2 during annealing"
Lingfeng He, Xianming Bai, Janne Pakarinen, Brian Jaques, Jian Gan, Andrew Nelson, Anter EL-AZAB, Todd Allen,
Journal of Nuclear Materials
Vol. 496
2017
242-250
Link
Transmission electron microscopy observation of Kr bubble evolution in polycrystalline UO2 annealed at high temperature was conducted in order to understand the inert gas behavior in oxide nuclear fuel. The average diameter of intragranular bubbles increased gradually from 0.8 nm in as-irradiated sample at room temperature to 2.6 nm at 1600 °C and the bubble size distribution changed from a uniform distribution to a bimodal distribution above 1300 °C. The size of intergranular bubbles increased more rapidly than intragranular ones and bubble denuded zones near grain boundaries formed in all the annealed samples. It was found that high-angle grain boundaries held bigger bubbles than low-angle grain boundaries. Complementary atomistic modeling was conducted to interpret the effects of grain boundary character on the Kr segregation. The area density of strong segregation sites in the high-angle grain boundaries is much higher than that in the low angle grain boundaries. |
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"Bubble formation and Kr distribution in Kr-irradiated UO2"
Todd Allen, Anter EL-AZAB, Jian Gan, Mahima Gupta, Andrew Nelson, Janne Pakarinen, Billy Valderrama, Lingfeng He, Abdel-Rahman Hassan, Hunter Henderson, Marquis Kirk, Michele Manuel,
Journal of Nuclear Materials
Vol. 456
2015
125-132
Link
In situ and ex situ transmission electron microscopy observation of small Kr bubbles in both single-crystal and polycrystalline UO2 were conducted to understand the inert gas bubble behavior in oxide nuclear fuel. The bubble size and volume swelling are shown as weak functions of ion dose but strongly depend on the temperature. The Kr bubble formation at room temperature was observed for the first time. The depth profiles of implanted Kr determined by atom probe tomography are in good agreement with the calculated profiles by SRIM, but the measured concentration of Kr is about 1/4 of the calculated concentration. This difference is mainly due to low solubility of Kr in UO2 matrix and high release of Kr from sample surface under irradiation. |
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"Bubble, stoichiometry, and chemical equilibrium of krypton-irradiated UO2"
Todd Allen, Anter EL-AZAB, Jian Gan, Mahima Gupta, Lingfeng He, Michele Manuel, Janne Pakarinen, Billy Valderrama, Abdel-Rahman Hassan, Marquis Kirk, Andrew Nelson,
Journal of Nuclear Materials
Vol. 456
2015
125-132
Link
In situ and ex situ transmission electron microscopy observation of small Kr bubbles in bothsingle-crystal and polycrystalline UO2 were conducted to understand the inert gas bubblebehavior in oxide nuclear fuel. The bubble size and volume swelling are shown as a weakfunction of ion dose but strongly depend on the temperature. The Kr bubble formation at roomtemperature was observed for the first time. The depth profiles of implanted Kr determined byatom probe tomography are in good agreement with the calculated profiles by SRIM, but themeasured concentration of Kr is about 1/3 of calculated one. This difference is mainly due to lowsolubility of Kr in UO2 matrix, which has been confirmed by both density-functional theorycalculations and chemical equilibrium analysis. |
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"Determining Oxidation States of Transition Metals in Molten Salt Corrosion using Electron Energy Loss Spectroscopy"
Lingfeng He, Kaustubh Bawane, Panayotis Manganaris, Yachun Wang,
Scripta Materialia
Vol. 197
[unknown]
113790
Link
This work utilizes electron energy loss spectroscopy (EELS) to identify oxidation state of alloying elements in Ni-based alloys after exposure to molten chloride salt systems. Pure Ni and Ni-20Cr model alloy were corroded in molten ZnCl2 and KCl-MgCl2 under argon atmosphere at various temperatures. Oxidation states of Cr (Cr3+) and Ni (Ni2+) in the molten salt after corrosion were determined by monitoring changes in the L2,3 edges of corresponding EELS spectra. Oxidation state mapping technique using principal component analysis and multiple linear least squares fitting in HyperSpy Python package was developed. |
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"Early-stage microstructural evolution and phase stability in neutron-irradiated ferritic-martensitic steel T91" Huan Yan, Xiang Liu, Lingfeng He, James Stubbins, Journal of Nuclear Materials Vol. 557 2021 Link | ||
"Effect of dpa rate on the temperature regime of void swelling in ion-irradiated pure chromium" Adam Gabriel, Laura Hawkins, Aaron French, Yongchang Li, Zhihan Hu, Lingfeng He, Pengyuan Xiu, Michael Nastasi, Frank Garner, Lin Shao, JNM Vol. 561 2022 Link | ||
"Effect of Grain Boundaries on Krypton Segregation Behavior in Irradiated Uranium Dioxide"
Todd Allen, Darryl Butt, Jian Gan, Lingfeng He, Hunter Henderson, Brian Jaques, Michele Manuel, Janne Pakarinen, Billy Valderrama,
Journal of Metals
Vol. 66
2014
2562-2568
Link
Fission products, such as krypton (Kr), are known to be insoluble within UO2, segregating toward grain boundaries and eventually leading to a lowering in thermal conductivity and fuel swelling. Recent computational studies have identi?ed that differences in grain boundary structure have a signi?cant effect on the segregation behavior of fission products. However, experimental work supporting these simulations is lacking. Atom probe tomography was used to measure the Kr distribution across grain boundaries in UO2. Polycrystalline depleted UO2 samples were irradiated with 0.7 MeV and 1.8 MeV Kr-ions and annealed to 1000C, 1300C, and 1600C for 1 h to produce a Kr-bubble dominated microstructure. The results of this work indicate a strong dependence of Kr concentration as a function of grain boundary structure. Temperature also influences grain boundary chemistry with greater Kr concentration evident at higher temperatures, resulting in a reduced Kr concentration in the bulk. Although Kr segregation takes place at elevated temperatures, no change in grain size or texture was observed in the irradiated UO2 samples. |
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"Effect of neutron irradiation on defect evolution in Ti3SiC2 and Ti2AlC"
Michel Barsoum, Lingfeng He, Elizabeth Hoffman, Gordon Kohse, Darin Tallman, Brenda Garcia-Diaz, Robert Sindelar,
Journal of Nuclear materials
Vol. 468
2015
1-13
Link
Herein we report on the characterization of defects formed in polycrystalline Ti3SiC2 and Ti2AlC samples
exposed to neutron irradiation e up to 0.1 displacements per atom (dpa) at 350 ± 40 C or 695 ± 25 C,
and up to 0.4 dpa at 350 ± 40 C. Black spots are observed in both Ti3SiC2 and Ti2AlC after irradiation to
both 0.1 and 0.4 dpa at 350 C. After irradiation to 0.1 dpa at 695 C, small basal dislocation loops, with a
Burgers vector of b ¼ 1/2 [0001] are observed in both materials. At 9 ± 3 and 10 ± 5 nm, the loop diameters
in the Ti3SiC2 and Ti2AlC samples, respectively, were comparable. At 1 1023 loops/m3, the
dislocation loop density in Ti2AlC wasz1.5 orders of magnitude greater than in Ti3SiC2, at 3 1021 loops/
m3. After irradiation at 350 C, extensive microcracking was observed in Ti2AlC, but not in Ti3SiC2. The
room temperature electrical resistivities increased as a function of neutron dose for all samples tested,
and appear to saturate in the case of Ti3SiC2. The MAX phases are unequivocally more neutron radiation
tolerant than the impurity phases TiC and Al2O3. Based on these results, Ti3SiC2 appears to be a more
promising MAX phase candidate for high temperature nuclear applications than Ti2AlC. |
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"Effect of proton pre-irradiation on corrosion of Zr-0.5Nb model alloys with different Nb distributions"
Zefeng Yu, Taeho Kim, Mukesh Bachhav, Xiang Liu, Adrien Couet, Lingfeng He,
Corrosion Science Volume 173
Vol. 173
2020
108790
Link
The effect of proton irradiation on corrosion rate of α-annealed and β-quenched Zr-0.5Nb alloys is investigated. The major focuses of this study are to understand i) if the nucleation of irradiation-induced platelets (IIPs)/nanoclusters requires dissolution of Nb-rich native precipitates, ii) if the irradiated native precipitates and interlaths are stable in the oxide, and iii) how much Nb content in the solid solution is suitable to lower the corrosion rate for Zr-Nb alloys. To answer these questions, the major characterization techniques used in this study are APT and (S)TEM/EDS to study the microstructure and microchemistry evolution following irradiation and oxidation. |
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"Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121-1085 C temperature range"
Michel Barsoum, Jian Gan, Elizabeth Hoffman, Darin Tallman, Lingfeng He, El'ad Caspi,
Journal of Nuclear Materials
Vol. 484
2017
120-134
Link
Herein we report on the formation of defects in response to neutron irradiation of polycrystalline Ti3SiC2 and Ti3AlC2 samples exposed to total fluences of ˜6 × 1020 n/m2, 5 × 1021 n/m2 and 1.7 × 1022 n/m2 at irradiation temperatures of 121(12), 735(6) and 1085(68)°C. These fluences correspond to 0.14, 1.6 and 3.4 dpa, respectively. After irradiation to 0.14 dpa at 121 °C and 735 °C, black spots are observed via transmission electron microscopy in both Ti3SiC2 and Ti3AlC2. After irradiation to 1.6 and 3.4 dpa at 735 °C, basal dislocation loops, with a Burgers vector of b = ½ [0001] are observed in Ti3SiC2, with loop diameters of 21(6) and 30(8) nm after 1.6 dpa and 3.4 dpa, respectively. In Ti3AlC2, larger dislocation loops, 75(34) nm in diameter are observed after 3.4 dpa at 735 °C, in addition to stacking faults. Impurity particles of TiC, as well as stacking fault TiC platelets in the MAX phases, are seen to form extensive dislocation loops under all conditions. Cavities were observed at grain boundaries and within stacking faults after 3.4 dpa irradiation, with extensive cavity formation in the TiC regions at 1085 °C. Remarkably, denuded zones on the order of 1 µm are observed in Ti3SiC2 after irradiation to 3.4 dpa at 735 °C. Small grains, 3–5 µm in diameter, are damage free after irradiation at 1085 °C at this dose. The results shown herein confirm once again that the presence of the A-layers in the MAX phases considerably enhance their irradiation tolerance. Based on these results, and up to 3.4 dpa, Ti3SiC2 remains a promising candidate for high temperature nuclear applications as long as the temperature remains >700 °C. |
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"Electron microscopy characterization of fast reactor MOX Joint Oxyde-Gaine (JOG)"
Fabiola Cappia, Brandon Miller, Jeffery Aguiar, Lingfeng He, Daniel Murray, Brian Frickey, John Stanek, Jason Harp,
Journal of Nuclear Materials
Vol. 531
2020
Link
The composition and crystal structure of the “Joint Oxyde Gaine” (JOG) has been investigated by means of electron microscopy. Microstructural characterization reveals a highly heterogeneous porous structure with inclusions containing both fission products and cladding components. Major fission products detected, other than Cs and Mo, are Te, I, Zr and Ba. The layer is composed by sub-micrometric crystallites. The diffraction data refinement, together with chemical mapping, confirms the presence of Cs2MoO4, which is the major component of the JOG. However, combinatorial analyses reveal that other non-stoichiometric phases are possible, highlighting the complex nature of the crystalline structure of the JOG.
Fe is found in metallic Pd-rich precipitates with structure compatible with the tetragonal structure of FePd alloy. Cr is found in different locations of the JOG, in oxide form, but no structural data could be obtained due to local beam sensitization of the sample in those areas. |
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"Enhanced Resistance to Irradiation Induced Ferritic Transformation in Nanostructured Austenitic Steels"
Andrew Hoffman, Maalavan Arivu, Haiming Wen, Li He, Kumar Sridharan, Xin Wang, Xiang Liu, Lingfeng He, Yaqiao Wu,
Materialia
Vol. 13
2020
Link
Irradiation induced phase transformation of γ-austenite to α-ferrite has been observed in austenitic steels for the past several decades. This transformation can be detrimental to structural materials in a nuclear reactor environment as the increased fraction of the ferritic phase can increase corrosion and embrittlement and lead to stress corrosion cracking. This transformation is caused by both strain induced martensite transformation as well as radiation induced segregation and precipitation. In this study, two radiation tolerant nanostructured 304L austenitic steels (one ultrafine grained and one nanocrystalline) were manufactured using severe plastic deformation. These nanostructured 304L steels were compared to conventional coarse-grained 304L, after self-ion irradiation at 500°C up to a peak damage of 50 displacements per atom. Phase fraction after irradiation was analyzed using grazing incidence x-ray diffraction, precession electron diffraction, and electron backscatter diffraction. Nanostructured 304L steels showed significant resistance to irradiation induced austenite to ferrite transformation. This resistance was shown to be due to a decrease in defect formation, as well as a reduction in radiation induced segregation and precipitation. |
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"Faulted and Perfect Loop Evolution in Single Crystal Thorium Dioxide under High-Temperature Proton Irradiation" Anshul Kamboj, Md Minaruzzaman, Kaustubh Bawane, Lingfeng He, Lin Shao, Marat Khafizov, Yongfeng Zhang, Miaomiao Jin, David Hurley, Boopathy Kombaiah, Journal of Nuclear Materials Vol. 615 2025 Link | ||
"Formation of tetragonal gas bubble superlattice in bulk molybdenum under helium ion implantation"
Cheng Sun, David Sprouster, Khalid Hattar, Lynne Ecker, Lingfeng He, Y. Gao, Yipeng Gao, Yongfeng Zhang, Jian Gan,
Scripta Materialia
Vol. 149
2018
26-30
Link
We report the formation of tetragonal gas bubble superlattice in bulk molybdenum under helium ion implantation at 573 K. The transmission electron microscopy study shows that the helium bubble lattice constant measured from the in-plane d-spacing is ~4.5 nm, while it is ~3.9 nm from the out-of-plane measurement. The results of synchrotron-based small-angle x-ray scattering agree well with the transmission electron microscopy results in terms of the measurement of bubble lattice constant and bubble size. The coupling of transmission electron microscopy and synchrotron high-energy X-ray scattering provides an effective approach to study defect superlattices in irradiated materials. |
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"Fuel-cladding chemical interaction of a prototype annular U-10Zr fuel with Fe-12Cr ferritic/martensitic HT-9 cladding" Xiang Liu, Luca Capriotti, Tiankai Yao, Jason Harp, Michael Benson, Yachun Wang, Fei Teng, Lingfeng He, https://www.sciencedirect.com/science/article/pii/S002231152031196X#ack0001 Vol. 544 2021 Link | ||
"Fuel-cladding chemical interation of a prototype annular U-10Zr fuel with HT-9 cladding"
Lingfeng He,
Journal of Nuclear Materials
Vol. 544
2021
As an alternative fuel form, the annular metallic fuel design eliminates the liquid sodium bond between the fuel and the cladding, providing back-end fuel cycle and other benefits. The fuel-cladding chemical interaction (FCCI) of annular fuel also presents new features. Here, state-of-the-art electron microscopy and spectroscopy techniques were used to study the FCCI of a prototype annular U-10wt%Zr (U-10Zr) fuel with ferritic/martensitic HT-9 cladding irradiated to 3.3% fission per initial heavy atom. Compared with sodium-bonded solid fuels, negligible amounts of lanthanides were found in the FCCI layer in the investigated helium-bonded annular fuel. Instead, most lanthanides were retained in the newly formed UZr2 phase in the fuel center region. The interdiffusion of iron and uranium resulted in tetragonal (U,Zr)6Fe phase (space group I4/mcm) and cubic (U,Zr)(Fe,Cr)2 phase (space group Fdm). The (U,Zr)(Fe,Cr)2phase contains a high density of voids and intergranular uranium monocarbides of NaCl-type crystal structure (space group Fmm). At the interdiffusion zone and inner cladding interface, a porous lamellar structure composed of alternating Cr-rich layers and U-rich layers was observed. Next to the lamellar region, the unexpected phase transformation from body-centered cubic ferrite (α-Fe) to tetragonal binary Fe-Cr σ phase (space group P42/mnm) occurred, and tetragonal Fe-Cr-U-Si phase (space group I4/mmm) was identified. Due to the diffusion of carbon into the interdiffusion zone, carbon depletion inside the HT-9 led to the disappearance of the martensite lath structure, and intergranular U-rich carbides formed as a result of the diffusion of uranium into the cladding. These detailed new findings reveal the unique features of the FCCI behavior of annular U-Zr fuels, which could be a promising alternative fuel form for high burnup fast reactor applications. |
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"Fullerene-like defects in high-temperature neutron-irradiated nuclear graphite"
Lingfeng He,
Carbon
Vol. 166
2020
Pages 113-122
Irradiation-induced defect evolution in graphite is particularly important for its application in graphite-moderated nuclear reactors. The evolution of defects directly influences macroscopically observed property changes in irradiated nuclear graphite which, in turn, can govern the lifetime of graphite components. This article reports novel defect structures and the irradiation response of microstructural features occurring in high-temperature irradiated nuclear graphite IG-110. High resolution transmission electron microscopy (HRTEM) was used to characterize specimens neutron-irradiated at a high temperature (≥800 °C) at doses of 1.73 and 3.56 atomic displacements per atom (dpa). Concentric shelled and fullerene-like defects were found to result in swelling along the c-axis and contraction along the a/b-axis of crystallites. Furthermore, such defects are shown to occur within, and partially fill, Mrozowski cracks prior to turnaround dose. In addition, in situ TEM under similar irradiation conditions was used to capture the real-time dynamic evolution of defects, providing unambiguous analysis of the evolution of the graphite structures during irradiation. Results suggest the mainstream theory for radiation damage in nuclear graphite (which assumes additional basal plane formation as the sole reason) to be an incorrect interpretation of defect evolution contributing to irradiation-induced property changes at higher temperatures. |
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"Hydrothermal synthesis of silicon oxide clad uranium oxide nanowires" Lingfeng He, Jason Harp, Adrian Wagner, Rita Hoggan, Kevin Tolman, Journal of the American Cermic Society Vol. 2018 1004-1008 Link | ||
"Impact of krypton irradiation on a single crystal tungsten: Multi-modal X-ray imaging study"
Lingfeng He,
Scripta Materialia
Vol. 188
2020
296-301
Link
Understanding microstructural and strain evolutions induced by noble gas production in the nuclear fuel matrix or plasma-facing materials is crucial for designing next generation nuclear reactors, as they are responsible for volumetric swelling and catastrophic failure. We describe a multimodal approach combining synchrotron-based nanoscale X-ray imaging techniques with atomic-scale electron microscopy techniques for mapping chemical composition, morphology and lattice distortion in a single crystal W induced by Kr irradiation. We report that Kr-irradiated single crystal W undergoes surface deformation, forming Kr containing cavities. Furthermore, positive strain fields are observed in Kr-irradiated regions, which lead to compression of underlying W matrix. |
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"In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation"
Michael Moorehead, Calvin Parkin, Mohamed Elbakhshwan, Jing Hu, Wei-Ying Chen, Meimei Li, Lingfeng He, Kumar Sridharan, Adrien Couet,
Acta Materialia
Vol. 198
2020
85-99
Link
This study characterizes the microstructural evolution of single-phase complex concentrated solid-
solution alloy (CSA) compositions under heavy ion irradiation with the goal of evaluating mecha-
nisms for CSA radiation tolerance in advanced fission systems. Three such alloys, Cr 18 Fe 27 Mn 27 Ni 28 ,
Cr 15 Fe 35 Mn 15 Ni 35 , and equimolar NbTaTiV, along with reference materials (pure Ni and E90 for the Cr-
FeMnNi family and pure V for NbTaTiV) were irradiated at 50 K and 773 K with 1 MeV Kr ++ ions to vari-
ous levels of displacements per atom (dpa) using in-situ transmission electron microscopy. Cryogenic irra-
diation resulted in small defect clusters and faulted dislocation loops as large as 12 nm in face-centered
cubic (FCC) CSAs. With thermal diffusion suppressed at cryogenic temperatures, defect densities were
lower in all CSAs than in their less compositionally complex reference materials indicating that point
defect production is reduced during the displacement cascade stage. High temperature irradiation of the
two FCC CSA resulted in the formation of interstitial dislocation loops which by 2 dpa grew to an average
size of 27 nm in Cr 18 Fe 27 Mn 27 Ni 28 and 10 nm in Cr 15 Fe 35 Mn 15 Ni 35 . This difference in loop growth kinet-
ics was attributed to the difference in Mn-content due to its effect on the nucleation rate by increasing
vacancy mobility or reducing the stacking-fault energy.#171118 |
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"In Situ TEM Observation of Dislocation Evolution in Polycrystalline UO2"
Todd Allen, Jian Gan, Mahima Gupta, Janne Pakarinen, Lingfeng He, Marquis Kirk,
JOM
Vol. 66
2014
2553-2561
Link
In situ transmission electron microscopy observation of polycrystalline UO2 (with average grain size of about 5 µm) irradiated with Kr ions at 600°C and 800°C was conducted to understand the radiation-induced dislocation evolution under the influence of grain boundaries. The dislocation evolution in the grain interior of polycrystalline UO2 was similar under Kr irradiation at different ion energies and temperatures. As expected, it was characterized by the nucleation and growth of dislocation loops at low irradiation doses, followed by transformation to extended dislocation lines and tangles at high doses. For the first time, a dislocation-denuded zone was observed near a grain boundary in the 1-MeV Kr-irradiated UO2 sample at 800°C. The denuded zone in the vicinity of grain boundary was not found when the irradiation temperature was at 600°C. The suppression of dislocation loop formation near the boundary is likely due to the enhanced interstitial diffusion toward grain boundary at the high temperature. |
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"Measurement of grain boundary strength of Inconel X-750 superalloy using in-situ micro-tensile testing techniques in FIB/SEM system" Yachun Wang, Xiang Liu, Daniel Murray, Fei Teng, Wen Jiang, Mukesh Bachhav, Laura Hawkins, Emmanuel Perez, Cheng Sun, Xianming Bai, Jie Lian, Colin Judge, John Jackson, Robert Carter, Lingfeng He, Materials Science & Engineering Vol. 849 2022 Link | ||
"Microstructural changes of proton irradiated Hastelloy-N and in situ micropillar compression testing of one single grain at different local damage levels" Miguel Pena, Andres Morell-Pacheco, Ching-Heng Shiau, Boopathy Kombaiah, Lingfeng He, Laura Hawkins, Adam Gabriel, Frank Garner, Lin Shao, JNM Vol. 2022 Link | ||
"Microstructure changes and thermal conductivity reduction in UO2 following 3.9 MeV He2+ ion irradiation"
Janne Pakarinen, Marat Khafizov, Lingfeng He, Jian Gan, Anter EL-AZAB, Andrew Nelson, Chris Wetteland, David Hurley, Todd Allen,
Journal of Nuclear Materials
Vol. 454
2014
283-289
Link
The microstructural changes and associated effects on thermal conductivity were examined in UO2 after irradiation using 3.9 MeV He2+ ions. Lattice expansion of UO2 was observed in X-ray diffraction after ion irradiation up to 5 × 1016 He2+/cm2 at low-temperature (<200 °C). Transmission electron microscopy (TEM) showed homogenous irradiation damage across an 8 μm thick plateau region, which consisted of small dislocation loops accompanied by dislocation segments. Dome-shaped blisters were observed at the peak damage region (depth around 8.5 μm) in the sample subjected to 5 × 1016 He2+/cm2, the highest fluence reached, while similar features were not detected at 9 × 1015 He2+/cm2. Laser-based thermo-reflectance measurements showed that the thermal conductivity for the irradiated layer decreased about 55% for the high fluence sample and 35% for the low fluence sample as compared to an un-irradiated reference sample. Detailed analysis for the thermal conductivity indicated that the conductivity reduction was caused by the irradiation induced point defects. |
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"Microstructure evolution in Xe-irradiated UO2 at room temperature"
Todd Allen, Anter EL-AZAB, Jian Gan, Lingfeng He, Janne Pakarinen, Marquis Kirk, Andrew Nelson, Xianming Bai,
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms
Vol. 330
2014
55-60
Link
In situ Transmission Electron Microscopy was conducted for single crystal UO2 to understand the microstructure evolution during 300 keV Xe irradiation at room temperature. The dislocation microstructure evolution was shown to occur as nucleation and growth of dislocation loops at low irradiation doses, followed by transformation to extended dislocation segments and tangles at higher doses. Xe bubbles with dimensions of 1-2 nm were observed after room-temperature irradiation. Electron Energy Loss Spectroscopy indicated that UO2 remained stoichiometric under room temperature Xe irradiation. |
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"On Spinodal-like Phase Decomposition in U-50 Zr Alloy"
Lingfeng He,
Materialia
Vol. 9
2020
Link
Finely dispersed two phase microstructures resulting from a spinodal decomposition are of interest as they are associated with enhanced mechanical properties and excessive interfaces to mitigate defect related behavior. This study reports a spinodal-like phase decomposition in a U–50Zr alloy by thermal annealing at 620 °C and ion irradiation at 550 °C, with the latter temperature too low to initiate pure thermal phase transformation. The results hold broad impact for U–Zr alloy systems and its application as advanced nuclear fuel. |
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"Phase and Defect Evolution in Uranium-Nitrogen-Oxygen System under Irradiation"
Lingfeng He,
Acta Materialia
Vol.
2021
Link
Uranium mononitride (UN) with 5 wt.% uranium dioxide (UO2) is used as a model system to study the phase and defect evolution under proton irradiation in nitride-oxide composite. Phase composition, crystallographic orientation relationships (ORs) and dislocation loops were characterized using X-ray diffraction, transmission electron microscopy, and energy dispersive X-ray spectroscopy techniques. Proton-irradiation at elevated temperatures promoted the transformation of UN into uranium sesquinitride (U2N3) and UO2 phases. U2N3 and UO2 formed a fully coherent structure with two ORs: {002}U2N3‖{002}UO2 and [001]U2N3‖[001]UO2; U2N3{101}‖UO2{101} and U2N3[101]‖UO2[101] due to low lattice misfit (2.3%) and low interfacial energy (127 mJ/m2). Observed oxidation of UN and coherent interface are consistent with density-functional theory calculations which suggest lower energy for oxidized configuration and low energy of the interface. The dislocation loops grew while their number density decreased with the temperature and dose. The loop size was over three times larger in two nitride phases than that in UO2, while the number density was one order of magnitude higher in UO2 than in nitride phases. Loop density and diameter were analyzed using a kinetic rate theory that considers stoichiometric loop evolution. This analysis led to the conclusion in all compounds loop growth is governed by mobility of uranium interstitials, and enabled measurement of diffusion coefficients of uranium interstitials and non-metal interstitials and vacancies. This analysis provided a comparative study of early stage of microstructure evolution under irradiation which has implications for use of this mixture as advanced fuel in nuclear energy systems. |
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"Radiation-induced grain subdivision and bubble formation in U3Si2 at LWR temperature"
Bowen Gong, Jason Harp, Jie Lian, Tiankai Yao, Lingfeng He, Michael Tonks,
Journal of Nuclear Materials
Vol. 498
2017
169-175
Link
U3Si2, an advanced fuel form proposed for light water reactors (LWRs), has excellent thermal conductivity and a high fissile element density. However, limited understanding of the radiation performance and fission gas behavior of U3Si2 is available at LWR conditions. This study explores the irradiation behavior of U3Si2 by 300 keV Xe+ ion beam bombardment combining with in-situ transmission electron microscopy (TEM) observation. The crystal structure of U3Si2 is stable against radiation-induced amorphization at 350 °C even up to a very high dose of 64 displacements per atom (dpa). Grain subdivision of U3Si2 occurs at a relatively low dose of 0.8 dpa and continues to above 48 dpa, leading to the formation of high-density nanoparticles. Nano-sized Xe gas bubbles prevail at a dose of 24 dpa, and Xe bubble coalescence was identified with the increase of irradiation dose. The volumetric swelling resulting from Xe gas bubble formation and coalescence was estimated with respect to radiation dose, and a 2.2% volumetric swelling was observed for U3Si2 irradiated at 64 dpa. Due to extremely high susceptibility to oxidation, the nano-sized U3Si2 grains upon radiation-induced grain subdivision were oxidized to nanocrystalline UO2 in a high vacuum chamber for TEM observation, eventually leading to the formation of UO2 nanocrystallites stable up to 80 dpa. |
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"STEM-EDS/EELS and APT characterization of ZrN coatings on UMo fuel kernels" Lingfeng He, Mukesh Bachhav, Dennis Keiser, Emmanuel Perez, Brandon Miller, Jian Gan, Ann Leenaers, Sven Van den Berghe, Journal of Nuclear Materials Vol. 511 2018 174-182 Link | ||
"Subsurface imaging of grain microstructure using picosecond ultrasonics"
Darryl Butt, Hunter Henderson, David Hurley, Brian Jaques, Marat Khafizov, Andrew Nelson, Janne Pakarinen, Michele Manuel, Lingfeng He,
Acta Materialia
Vol. 112
2016
1476-1477
Link
We report on imaging subsurface grain microstructure using picosecond ultrasonics. This approach relies on elastic anisotropy of crystalline materials where ultrasonic velocity depends on propagation direction relative to the crystal axes. Picosecond duration ultrasonic pulses are generated and detected using ultrashort light pulses. In materials that are transparent or semitransparent to the probe wavelength, the probe monitors gigahertz frequency Brillouin oscillations. The frequency of these oscillations is related to the ultrasonic velocity and the optical index of refraction. Ultrasonic waves propagating across a grain boundary experience a change in velocity due to a change in crystallographic orientation relative to the ultrasonic propagation direction. This change in velocity is manifested as a change in the Brillouin oscillation frequency. Using the ultrasonic propagation velocity, the depth of the interface can be determined from the location in time of the transition in oscillation frequency. A subsurface image of the grain boundary is obtained by scanning the beam along the surface. We demonstrate this subsurface imaging capability using a polycrystalline UO2 sample. Cross section liftout analysis of the grain boundary using electron microscopy was used to verify our imaging results. |
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"TEM Characterization of Dislocation Loops in Proton Irradiated Single Crystal ThO2" Marat Khafizov, Kaustubh Bawane, Tiankai Yao, Aaron French, James Mann, Lin Shao, Jian Gan, David Hurley, Lingfeng He, Journal of Nuclear Materials Vol. 552 2021 Link | ||
"The influence of lattice defects, recombination, and clustering on thermal transport in single crystal thorium dioxide"
Lingfeng He,
APL Materials
Vol. 8
2020
Link
Thermal transport is a key performance metric for thorium dioxide in many applications where defect-generating radiation fields are present. An understanding of the effect of nanoscale lattice defects on thermal transport in this material is currently unavailable due to the lack of a single crystal material from which unit processes may be investigated. In this work, a series of high-quality thorium dioxide single crystals are exposed to 2 MeV proton irradiation at room temperature and 600 °C to create microscale regions with varying densities and types of point and extended defects. Defected regions are investigated using spatial domain thermoreflectance to quantify the change in thermal conductivity as a function of ion fluence as well as transmission electron microscopy and Raman spectroscopy to interrogate the structure of the generated defects. Together, this combination of methods provides important initial insight into defect formation, recombination, and clustering in thorium dioxide and the effect of those defects on thermal transport. These methods also provide a promising pathway for the quantification of the smallest-scale defects that cannot be captured using traditional microscopy techniques and play an outsized role in degrading thermal performance |
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"Thermal stability of helium bubble superlattice in Mo under TEM in-situ heating"
Jian Gan, Cheng Sun, Lingfeng He, Yongfeng Zhang, Chao Jiang, Yipeng Gao,
Journal of Nuclear Materials
Vol. 505
2018
207-211
Link
Although the temperature window of helium ion irradiation for gas bubble superlattice (GBS) formation was found to be in the range of approximately 0.15–0.35 melting point in literature, the thermal stability of He GBS has not been fully investigated. This work reports the experiment using an in-situ heating holder in a transmission electron microscope (TEM). A 3.0 mm TEM disc sample of Mo (99.95% pure) was irradiated with 40 keV He ions at 300 °C to a fluence of 1.0E+17 ions/cm2, corresponding to a peak He concentration of approximately 10 at.%, in order to introduce He GBS. In-situ heating was conducted with a ramp rate of ∼25 °C/min, hold time of ∼30 min, and temperature step of ∼100 °C up to 850 °C (0.39Tm homologous temperature). The result shows good thermal stability of He GBS in Mo with no noticeable change on GBS lattice constant and ordering. The implication of this unique and stable ordered microstructure on mechanistic understanding of GBS and its advanced application are discussed. |
"Advanced Characterization of Irradiated UO2 Fuel" Lingfeng He, Michael Moorehead, Brandon Miller, Jason Harp, Xianming Bai, TMS 2018 March 11-15, (2018) | |
"Comparison of Computationally Simulated Fission Product Distribution with Correlative Characterization Techniques in Surrogate Nuclear Fuel Materials" Todd Allen, Jian Gan, Lingfeng He, Hunter Henderson, Michele Manuel, Billy Valderrama, 2013 SACNAS National Conference October 2-6, (2013) | |
"Electron microscopy characterization of fast reactor MOX joint-oxide-gaine (JOG)" Fabiola Cappia, Brandon Miller, Daniel Murray, Lingfeng He, Brian Frickey, John Stanek, Jason Harp, EMRS 2019 May 27-31, (2019) | |
"Fission Products in Nuclear Fuel: Comparison of Simulated Distribution with Correlative Characterization Techniques" Todd Allen, Anter EL-AZAB, Jian Gan, Lingfeng He, Hunter Henderson, Michele Manuel, Billy Valderrama, Clarissa Yablinsky, Microscopy and Microanalysis August 4-8, (2012) | |
"Influence of Irradiation-induced Microstructural Defects on the Thermal Conductivity of Single Crystal Thorium Dioxide" Marat Khafizov, Amey Khanolkar, Zilong Hua, Cody Dennett, wangthink Wang, Tiankai Yao, Lingfeng He, Jian Gan, David Hurley, TMS 2020 February 23-27, (2020) | |
"Microstructural Characterization of High-entropy Alloy Ion Irradiated at Cryogenic Temperatures" Michael Moorehead, Calvin Parkin, Lingfeng He, Jing Hu, Meimei Li, Adrien Couet, Kumar Sridharan, TMS 2019 March 10-14, (2019) | |
"Microstructural Defects in Neutron Irradiated Ti3SiC2 and Ti2AlC" Michel Barsoum, Lingfeng He, Elizabeth Hoffman, Gordon Kohse, Darin Tallman, ICACC'15 January 25-29, (2015) | |
"Microstructural Investigation of Kr Irradiated UO2" Todd Allen, Jian Gan, Mahima Gupta, Lingfeng He, Clarissa Yablinsky, The Minerals, Materials, and Metals Society, 2013 Annual Meeting & Exhibition March 3-7, (2013) | |
"Microstructural Investigations of Kr and Xe Irradiated UO2" Todd Allen, Anter EL-AZAB, Jian Gan, Mahima Gupta, Lingfeng He, Hunter Henderson, Michele Manuel, Janne Pakarinen, Billy Valderrama, Energy Frontier Research Centers Principal Investigators Meeting July 18-19, (2013) | |
"Nano-scale Irradiation Induced Chemistry Changes in Oxide" Todd Allen, Jian Gan, Lingfeng He, Hunter Henderson, Michele Manuel, Janne Pakarinen, Billy Valderrama, 2014 TMS Annual Meeting February 16-20, (2014) | |
"Neutron Irradiation of MAX Phases" Michel Barsoum, Lingfeng He, Elizabeth Hoffman, Gordon Kohse, Darin Tallman, Il Trovatore Meeting 2 July 23-25, (2015) | |
"Nuclear Scientific User Facility: Neutron Irradiation of MAX Phases" Michel Barsoum, Lingfeng He, Elizabeth Hoffman, Gordon Kohse, Darin Tallman, NSUF User's Week June 22-26, (2015) | |
"Poster - Examining microstructural differences in irradiated HT9 correlated with differences in processing prior to irradiation" Theresa Mary Green, Li He, Todd Allen, Brandon Miller, Lingfeng He, NUMAT 2018 October 15-18, (2018) | |
"Recent observations from the microstructural characterization of irradiated U-Mo fuels using advanced techniques" Dennis Keiser, Brandon Miller, Jian Gan, Lingfeng He, Daniel Jadernas, Mukesh Bachhav, NUMAT 2018 October 15-18, (2018) |
U.S. DOE Nuclear Science User Facilities Awards 30 Rapid Turnaround Experiment Research Proposals - Awards total nearly $1.2 million The U.S. Department of Energy (DOE) Nuclear Science User Facilities (NSUF) has selected 30 new Rapid Turnaround Experiment (RTE) projects, totaling up to approximately $1.2 million. These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy. Wednesday, April 26, 2017 - Calls and Awards |
DOE Awards 33 Rapid Turnaround Experiment Research Proposals - Projects total approximately $1.5 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy. Monday, May 14, 2018 - Calls and Awards |
DOE awards 39 RTE Projects - Projects total approximately $1.3 million Thursday, February 1, 2018 - Calls and Awards |
NSUF Researcher Feature: Lingfeng He - An instrumentation scientist at INL, He works with users to characterize fuel and materials The TEM group leader for INL, He manages the two TEMs in INL's Irradiated Materials and Characterization Laboratory, and it continually making sure that his group's expertise is cutting edge, but also that users have access to that expertise via NSUF. Monday, October 7, 2019 - Newsletter, Researcher Highlight |
NSUF awards 30 Rapid Turnaround Experiment proposals - Approximately $1.53M has been awarded. Tuesday, June 14, 2022 - Calls and Awards |
NSUF awards 28 Rapid Turnaround Experiment proposals - Approximately $1.74M has been awarded. The new call closes June 28. Thursday, June 1, 2023 - Calls and Awards |
"Transmission electron microscopy investigation of phase transformation and fuel constituent redistribution in neutron irradiated U-10wt.%Zr fuel" Xiang Liu, Lingfeng He, Daniel Murray, Fei Teng, Boopathy Kombaiah, Alex Winston, Maria A. Okuniewski, Jonova Thomas, [2023] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154443 | |
"Microstructural changes of proton irradiated Hastelloy-N and in situ micropillar compression testing of one single grain at different local damage levels" Andres Morell-Pacheco, Ching-Heng Shiau, Boopathy Kombaiah, Lingfeng He, Laura Hawkins, Adam Gabriel, Frank A. Garner, Lin Shao, Miguel Pena, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153939 | |
"Comprehensive characterization of irradiation induced defects in ceria: Impact of point defects on vibrational and optical properties"
Joshua Ferrigno, Saqeeb Adnan, Janne Pakarinen, Lingfeng He, David H. Hurley, Marat Khafizov, Vinay S. Chauhan,
[2022]
Journal of Applied Physics
· DOI: 10.1063/5.0099189
Validation of multiscale microstructure evolution models can be improved when standard microstructure characterization tools are coupled with methods sensitive to individual point defects. We demonstrate how electronic and vibrational properties of defects revealed by optical absorption and Raman spectroscopies can be used to compliment transmission electron microscopy (TEM) and x-ray diffraction (XRD) in the characterization of microstructure evolution in ceria under non-equilibrium conditions. Experimental manifestation of non-equilibrium conditions was realized by exposing cerium dioxide (CeO2) to energetic protons at elevated temperature. Two sintered polycrystalline CeO2 samples were bombarded with protons accelerated to a few MeVs. These irradiation conditions produced a microstructure with resolvable extended defects and a significant concentration of point defects. A rate theory (RT) model was parametrized using the results of TEM, XRD, and thermal conductivity measurements to infer point defect concentrations. An abundance of cerium sublattice defects suggested by the RT model is supported by Raman spectroscopy measurements, which show peak shift and broadening of the intrinsic T2g peak and emergence of new defect peaks. Additionally, spectroscopic ellipsometry measurements performed in lieu of optical absorption reveals the presence of Ce3+ ions associated with oxygen vacancies. This work lays the foundation for a coupled approach that considers a multimodal characterization of microstructures to guide and validate complex defect evolution models. |
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"Dislocation loop evolution in Kr‐irradiated ThO2"
Tiankai Yao, Kaustubh Bawane, Miaomiao Jin, Chao Jiang, Xiang Liu, Wei‐Ying Chen, J. Matthew Mann, David H. Hurley, Jian Gan, Marat Khafizov, Lingfeng He,
[2022]
Journal of the American Ceramic Society
· DOI: 10.1111/jace.18478
The early stage of microstructural evolution of ThO2, under krypton irradiation at 600, 800, and 1000°C, was investigated using in situ transmission electron microscopy (TEM). Dislocation loops grew faster, whereas their number density decreased with increasing irradiation temperature. Loop density was found to decrease with ion dose. Interstitial dislocation loops, including Frank loops with Burgers vector of |
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"Synthesis and characterization of uranium trichloride in alkali-metal chloride media" Haiyan Zhao, Kaustubh K. Bawane, Lingfeng He, Kevin R. Tolman, Xiaofei Pu, Steven D. Herrmann, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153728 | |
"Unraveling small-scale defects in irradiated ThO2 using kinetic Monte Carlo simulations" Lingfeng He, Cody A. Dennett, Marat Khafizov, J. Matthew Mann, David H. Hurley, Chao Jiang, [2022] Scripta Materialia · DOI: 10.1016/j.scriptamat.2022.114684 | |
"Compositionally graded specimen made by laser additive manufacturing as a high-throughput method to study radiation damages and irradiation-assisted stress corrosion cracking" Laura Hawkins, Miao Song, Lingfeng He, Mukesh Bachhav, Qingyu Pan, Lin Shao, Daniel Schwen, Xiaoyuan Lou, Jingfan Yang, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153493 · ISSN: 0022-3115 | |
"Thermal Energy Transport in Oxide Nuclear Fuel" Anter El-Azab, Matthew S. Bryan, Michael W. D. Cooper, Cody A. Dennett, Krzysztof Gofryk, Lingfeng He, Marat Khafizov, Gerard H. Lander, Michael E. Manley, J. Matthew Mann, Chris A. Marianetti, Karl Rickert, Farida A. Selim, Michael R. Tonks, Janelle P. Wharry, David H. Hurley, [2022] Chemical Reviews · DOI: 10.1021/acs.chemrev.1c00262 | |
"Sensitization, desensitization, and carbide evolution of Alloy 800H made by laser powder bed fusion" Xiang Liu, Miao Song, Lingfeng He, Stephen Bankson, Michael Hamilton, Bart Prorok, Xiaoyuan Lou, Jingfan Yang, [2022] Additive Manufacturing · DOI: 10.1016/j.addma.2021.102547 · ISSN: 2214-8604 | |
"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" Xiaoyang Liu, Ruchi Gakhar, Michael Woods, Mingyuan Ge, Xianghui Xiao, Wah-Keat Lee, Philip Halstenberg, Sheng Dai, Shannon Mahurin, Simon M. Pimblott, James F. Wishart, Yu-chen Karen Chen-Wiegart, Lingfeng He, Kaustubh Bawane, [2022] Corrosion Science · DOI: 10.1016/j.corsci.2021.109962 · ISSN: 0010-938X | |
"Chemical and elemental mapping of spent nuclear fuel sections by soft X-ray spectromicroscopy"
Danil E. Smiles, Daniel Lussier, Alison B. Altman, Mukesh Bachhav, Lingfeng He, Michael W. Mara, Claude Degueldre, Stefan G. Minasian, David K. Shuh, Alexander Scott Ditter,
[2022]
Journal of Synchrotron Radiation
· DOI: 10.1107/s1600577521012315
Soft X-ray spectromicroscopy at the O |
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"Preparation and strengthening mechanism of prestressed ceramic tile components"
Tianye Wu, Yiwang Bao, Yueming Li, Detian Wan, Kai Li, Lingfeng He, Yi Sun,
[2022]
International Journal of Applied Ceramic Technology
· DOI: 10.1111/ijac.13757
To improve the flexural strength of ceramic tiles, a surface strengthening method is presented in this work. By cofiring coating and substrate, residual compressive stress is introduced in the coating. The phase composition and morphological characteristics of coating materials and the influences of coefficient of thermal expansion (CTE) and coating thickness on the flexural strength have been investigated. The prestressed ceramic tile is prepared by pressureless sintering a green body coated with a low CTE coating at 1200°C. The CTE of green body and optimal coating is 7.85 × 10−6°C−1 and 5.69 × 10−6°C−1, respectively. The flexural strength of prestressed porcelain tiles (89 ± 3 MP) has been increased by 102% when the coating thickness is 67 µm compared to their uncoated counterpart (44 ± 3 MPa). This simple surface strengthening method of ceramic tiles is cost‐efficient and economical for large‐scale industrial applications. |
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"Dislocation Loops in Proton Irradiated Uranium-Nitrogen-Oxygen System" Miaomiao Jin, Kaustubh Bawane, Beata Tyburska-Püschel, Brian J. Jaques, Kevin G. Field, Jeffrey J. Giglio, Lingfeng He, Pengyuan Xiu, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153244 · ISSN: 0022-3115 | |
"Early-stage microstructural evolution and phase stability in neutron-irradiated ferritic-martensitic steel T91" Xiang Liu, Lingfeng He, James Stubbins, Huan Yan, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153207 · ISSN: 0022-3115 | |
"Phase stability and microstructural evolution in neutron-irradiated ferritic-martensitic steel HT9" Xiang Liu, Lingfeng He, James Stubbins, Huan Yan, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153252 · ISSN: 0022-3115 | |
"Structure of the pellet-cladding interaction layer of a high-burnup Zr-Nb-O nuclear fuel cladding" Mahmut Nedim Cinbiz, Boopathy Kombaiah, Lingfeng He, Fei Teng, Evrard Lacroix, Xiang Liu, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153196 · ISSN: 0022-3115 | |
"Proton irradiation-induced blistering in UO2"
Lingfeng He, Jian Gan, Andrew T. Nelson, Anter El-Azab, Marat Khafizov, Todd R. Allen, Janne Pakarinen,
[2021]
MRS Advances
· DOI: 10.1557/s43580-021-00149-3
· ISSN: 2059-8521
Proton (H+) irradiation effects in polycrystalline UO2 have been studied. The irradiation was carried out using three ion energies and two different ion fluxes at 600 °C. Scanning electron microscopy (SEM) investigations showed that significant surface flaking took place. Focused ion beam (FIB) milling in SEM was successfully applied for extracting lamellas from uneven blistered surfaces for transmission electron microscopy (TEM) investigations allowing detailed investigations for the degradation mechanisms. High-resolution TEM for the flaked UO2 surfaces revealed that the implanted H+ formed sharp two-dimensional cavities at the peak ion-stopping region instead of diffusing to the matrix. The resulting lateral stress likely caused UO2 surface deterioration in good agreement with previous blistering and flaking studies on crystalline materials. |
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"Effects of heat treatment on corrosion fatigue and stress corrosion crack growth of additive-manufactured Alloy 800H in high-temperature water" Miao Song, Laura R. Hawkins, Xiang Liu, Lingfeng He, Xiaoyuan Lou, Jingfan Yang, [2021] Corrosion Science · DOI: 10.1016/j.corsci.2021.109739 · ISSN: 0010-938X | |
"Nanoscale redistribution of alloying elements in high-burnup AXIOM-2 (X2®) and their effects on in-reactor corrosion" Mukesh Bachhav, Fei Teng, Lingfeng He, Adrien Couet, Zefeng Yu, [2021] Corrosion Science · DOI: 10.1016/j.corsci.2021.109652 · ISSN: 0010-938X | |
"An integrated experimental and computational investigation of defect and microstructural effects on thermal transport in thorium dioxide" W. Ryan Deskins, Marat Khafizov, Zilong Hua, Amey Khanolkar, Kaustubh Bawane, Lyuwen Fu, J. Matthew Mann, Chris A. Marianetti, Lingfeng He, David H. Hurley, Anter El-Azab, Cody A. Dennett, [2021] Acta Materialia · DOI: 10.1016/j.actamat.2021.116934 | |
"Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation" Marat Khafizov, Chao Jiang, Beata Tyburska-Püschel, Brian J. Jaques, Pengyuan Xiu, Peng Xu, Mitchell K. Meyer, Kumar Sridharan, Darryl P. Butt, Jian Gan, Lingfeng He, [2021] Acta Materialia · DOI: 10.1016/j.actamat.2021.116778 | |
"Indirect characterization of point defects in proton irradiated ceria" Janne Pakarinen, Tiankai Yao, Lingfeng He, David H. Hurley, Marat Khafizov, Vinay S. Chauhan, [2021] Materialia · DOI: 10.1016/j.mtla.2021.101019 | |
"Thermal conductivity of ThO2: Effect of point defect disorder"
Ahmed Hamed, Tomohisa Kumagai, Cody A. Dennett, Jie Peng, Marat Khafizov, David Hurley, Anter El-Azab, W. Ryan Deskins,
[2021]
Journal of Applied Physics
· DOI: 10.1063/5.0038117
Thoria (ThO2) has lately gained attention due to its potential for use as a nuclear fuel. From a physics standpoint, ThO2 is an actinide-bearing material with no 5f electrons and is thus ideally suited as a baseline material for future studies of the physical properties of actinide systems with correlated electrons. Current investigations of ThO2 as a nuclear fuel focus on the influence of radiation-induced lattice defects on its thermal properties, especially the conductivity. This work presents a first investigation of the impact of point defect disorder on phonon thermal conductivity of ThO2 by solving the Boltzmann transport equation within the single-mode relaxation time approximation. The relaxation times of intrinsic, three-phonon scattering are calculated by a rigorous sampling of k-points within the irreducible Brillouin zone of the face-centered cubic crystal structure. The effect of point defects on the thermal conductivity of ThO2 is predicted using the classic model by Klemens for phonon relaxation times that result from the change in mass and induced lattice strain associated with point defects. Within this model, the change in force constants and atomic radii are computed using input from an atomistic model of ThO2. The defects considered are uranium substitution at a thorium site, oxygen vacancies and interstitials, and thorium vacancies and interstitials. The results show that the conductivity of ThO2 is highly sensitive to intrinsic point defects and less sensitive to U substitution on the cation sublattice. |
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"The influence of lattice defects, recombination, and clustering on thermal transport in single crystal thorium dioxide"
Zilong Hua, Amey Khanolkar, Tiankai Yao, Phyllis K. Morgan, Timothy A. Prusnick, Narayan Poudel, Aaron French, Krzysztof Gofryk, Lingfeng He, Lin Shao, Marat Khafizov, David B. Turner, J. Matthew Mann, David H. Hurley, Cody A. Dennett,
[2020]
APL Materials
· DOI: 10.1063/5.0025384
Thermal transport is a key performance metric for thorium dioxide in many applications where defect-generating radiation fields are present. An understanding of the effect of nanoscale lattice defects on thermal transport in this material is currently unavailable due to the lack of a single crystal material from which unit processes may be investigated. In this work, a series of high-quality thorium dioxide single crystals are exposed to 2 MeV proton irradiation at room temperature and 600 °C to create microscale regions with varying densities and types of point and extended defects. Defected regions are investigated using spatial domain thermoreflectance to quantify the change in thermal conductivity as a function of ion fluence as well as transmission electron microscopy and Raman spectroscopy to interrogate the structure of the generated defects. Together, this combination of methods provides important initial insight into defect formation, recombination, and clustering in thorium dioxide and the effect of those defects on thermal transport. These methods also provide a promising pathway for the quantification of the smallest-scale defects that cannot be captured using traditional microscopy techniques and play an outsized role in degrading thermal performance. |
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"Impact of krypton irradiation on a single crystal tungsten: Multi-modal X-ray imaging study" Mehmet Topsakal, Ericmoore Jossou, Xiaojing Huang, Khalid Hattar, Julia Mausz, Mohamed Elbakhshwan, Hanfei Yan, Yong S. Chu, Cheng Sun, Lingfeng He, Jian Gan, Lynne Ecker, Simerjeet K. Gill, [2020] Scripta Materialia · DOI: 10.1016/j.scriptamat.2020.07.024 · ISSN: 1359-6462 | |
"In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation" Michael Moorehead, Mohamed Elbakhshwan, Jing Hu, Wei-Ying Chen, Meimei Li, Lingfeng He, Kumar Sridharan, Adrien Couet, Calvin Parkin, [2020] Acta Materialia · DOI: 10.1016/j.actamat.2020.07.066 · ISSN: 1359-6454 | |
"Enhanced Resistance to Irradiation Induced Ferritic Transformation in Nanostructured Austenitic Steels" Maalavan Arivu, Haiming Wen, Li He, Kumar Sridharan, Xin Wang, Wei Xiong, Xiang Liu, Lingfeng He, Yaqiao Wu, Andrew Hoffman, [2020] Materialia · DOI: 10.1016/j.mtla.2020.100806 | |
"Fullerene-like defects in high-temperature neutron-irradiated nuclear graphite" Lingfeng He, Karen Bustillo, William E. Windes, Rick Ubic, Chinnathambi Karthik, Steve Johns, [2020] Carbon · DOI: 10.1016/j.carbon.2020.05.028 · ISSN: 0008-6223 | |
"Degradation mechanism of lead-vanado-iodoapatite in NaCl solution" Tiankai Yao, Fayuan Xi, Penghui Lei, Xiaolei Guo, Lingfeng He, Gerald S. Frankel, Jie Lian, Yachun Wang, [2020] Corrosion Science · DOI: 10.1016/j.corsci.2020.108720 · ISSN: 0010-938X | |
"Effect of proton pre-irradiation on corrosion of Zr-0.5Nb model alloys with different Nb distributions" Taeho Kim, Mukesh Bachhav, Xiang Liu, Lingfeng He, Adrien Couet, Zefeng Yu, [2020] Corrosion Science · DOI: 10.1016/j.corsci.2020.108790 · ISSN: 0010-938X | |
"The correlation between microstructure and nanoindentation property of neutron-irradiated austenitic alloy D9" Lingfeng He, Mack H. Cullison, Charles Hay, Jatuporn Burns, Yaqiao Wu, Lizhen Tan, Tianyi Chen, [2020] Acta Materialia · DOI: 10.1016/j.actamat.2020.05.020 | |
"Combining mesoscale thermal transport and x-ray diffraction measurements to characterize early-stage evolution of irradiation-induced defects in ceramics" M Faisal Riyad, Yuzhou Wang, Janne Pakarinen, Lingfeng He, Tiankai Yao, Anter El-Azab, David Hurley, Marat Khafizov, [2020] Acta Materialia · DOI: 10.1016/j.actamat.2020.04.018 | |
"Intragranular thermal transport in U–50Zr" Tiankai Yao, Amey Khanolkar, Xiaxin Ding, Krzysztof Gofryk, Lingfeng He, Michael Benson, David Hurley, Zilong Hua, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152145 · ISSN: 0022-3115 | |
"Dual Functional Ni3S2@Ni Core–Shell Nanoparticles Decorating Nanoporous Carbon as Cathode Scaffolds for Lithium–Sulfur Battery with Lean Electrolytes" Yuxiao Lin, Lingfeng He, Vijayakumar Murugesan, Gorakh Pawar, Bhuvana M. Sivakumar, Hanping Ding, Dong Ding, Boryann Liaw, Eric J. Dufek, Bin Li, Yulun Zhang, [2020] ACS Applied Energy Materials · DOI: 10.1021/acsaem.0c00568 · ISSN: 2574-0962 | |
"Development of a grain growth model for U3Si2 using experimental data, phase field simulation and molecular dynamics" Michael R. Tonks, Bowen Gong, Tiankai Yao, Lingfeng He, Jason M. Harp, Benjamin Beeler, Yongfeng Zhang, Jie Lian, Amani Cheniour, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152069 · ISSN: 0022-3115 | |
"Electron microscopy characterization of fast reactor MOX Joint Oxyde-Gaine (JOG)" B.D. Miller, J.A. Aguiar, L. He, D.J. Murray, B.J. Frickey, J.D. Stanek, J.M. Harp, F. Cappia, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.151964 · ISSN: 0022-3115 | |
"Experimental evidence for ‘buckle, ruck and tuck’ in neutron irradiated graphite" Lingfeng He, Joshua J. Kane, William E. Windes, Rick Ubic, Chinnathambi Karthik, Steve Johns, [2020] Carbon · DOI: 10.1016/j.carbon.2019.12.028 | |
"On spinodal-like phase decomposition in U–50Zr alloy" Adrian R Wagner, Xiang Liu, Anter EI-Azab, Jason M Harp, Jian Gan, David H Hurley, Michael T Benson, Lingfeng He, Tiankai Yao, [2020] Materialia · DOI: 10.1016/j.mtla.2020.100592 | |
"A transmission electron microscopy study of EBR-II neutron-irradiated austenitic stainless steel 304 and nickel-base alloy X-750" Lingfeng He, Huan Yan, Mukesh Bachhav, James F. Stubbins, Xiang Liu, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.151851 · ISSN: 0022-3115 | |
"A simple way to make pre-stressed ceramics with high strength" Fenghua Kuang, Yi Sun, Yueming Li, Detian Wan, Zongyang Shen, Delong Ma, Lingfeng He, Yiwang Bao, [2019] Journal of Materiomics · DOI: 10.1016/j.jmat.2019.06.001 · ISSN: 2352-8478 | |
"Impact of irradiation induced dislocation loops on thermal conductivity in ceramics"
Janne Pakarinen, Lingfeng He, David H. Hurley, Marat Khafizov,
[2019]
Journal of the American Ceramic Society
· DOI: 10.1111/jace.16616
Experimental work aimed at understanding the role of dislocation loops in limiting phonon mediated thermal transport in ceramics is presented. Faulted dislocation loops, having diameters of a few nanometers, were introduced by irradiating a polycrystalline cerium dioxide sample with 1.6 MeV protons at 700°C. XRD analysis indicated that irradiated samples retained their crystalline structure and exhibit very little lattice expansion suggesting a low concentration of point defects. Further microstructure characterization using transmission electron microscopy revealed that interstitial type faulted dislocation loops were primarily created as expected for these irradiation conditions. Thermal conductivity of the damaged layer was measured using a modulated thermoreflectance approach. Analysis of the experimental data using the classical Klemens‐Callaway approach reveals that the conductivity reduction is primarily due to dislocation loops, while point defects and voids play only a minor role. These results provide experimental confirmation that faulted loops offer a unique arrangement for displaced atoms that leads to an unusually large reduction of thermal conductivity. |
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"Diffusion behaviors between metallic fuel alloys with Pd addition and Fe" Michael T. Benson, Lingfeng He, James A. King, Robert D. Mariani, Daniel J. Murray, Yi Xie, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.07.028 · ISSN: 0022-3115 | |
"Microstructure and microchemistry study of irradiation-induced precipitates in proton irradiated ZrNb alloys" Chenyu Zhang, Paul M. Voyles, Lingfeng He, Xiang Liu, Kelly Nygren, Adrien Couet, Zefeng Yu, [2019] Acta Materialia · DOI: 10.1016/j.actamat.2019.08.012 | |
"Self-healing behavior and strength recovery of ytterbium disilicate ceramic reinforced with silicon carbide nanofillers" Tadachika Nakayama, Hisayuki Suematsu, Hirokazu Iwasawa, Tsuneo Suzuki, Yuichi Otsuka, Lingfeng He, Tsuyoshi Takahashi, Koichi Niihara, Son Thanh Nguyen, [2019] Journal of the European Ceramic Society · DOI: 10.1016/j.jeurceramsoc.2019.03.040 · ISSN: 0955-2219 | |
"Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln" Yi Xie, Lingfeng He, Kevin R. Tolman, James A. King, Jason M. Harp, Robert D. Mariani, Brandon J. Hernandez, Daniel J. Murray, Brandon D. Miller, Michael T. Benson, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.03.014 | |
"In-situ TEM study of the ion irradiation behavior of U3Si2 and U3Si5" Bowen Gong, Lingfeng He, Yinbin Miao, Jason M. Harp, Michael Tonks, Jie Lian, Tiankai Yao, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.08.058 | |
"STEM-EDS/EELS and APT characterization of ZrN coatings on UMo fuel kernels" M. Bachhav, D.D. Keiser, J.W. Madden, E. Perez, B.D. Miller, J. Gan, W. Van Renterghem, A. Leenaers, S. Van den Berghe, L. He, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.09.004 | |
"Evaluation of U 3 Si 2 Fuel Pellets Sintered in an Argon vs. Vacuum Environment" Jason Harp, Lingfeng He, Rita Hoggan, [2018] Ceramic Transactions Series · DOI: 10.1002/9781119543299.ch3 · ISSN: 2637-4390 | |
"Microstructural characterization of as-cast U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln" Lingfeng He, James A. King, Robert D. Mariani, Alexander J. Winston, James W. Madden, Michael T. Benson, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.05.062 | |
"Challenges and Opportunities on Elucidating Irradiated Fuels with Atom Probe Tomography" Jian Gan, Lingfeng He, Brandon Miller, Dennis Keiser, Mukesh Bachhav, [2018] Microscopy and Microanalysis · DOI: 10.1017/s1431927618011510 · ISSN: 1431-9276 | |
"Thermal stability of helium bubble superlattice in Mo under TEM in-situ heating" Cheng Sun, Lingfeng He, Yongfeng Zhang, Chao Jiang, Yipeng Gao, Jian Gan, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.04.030 | |
"Interdiffusion behavior of U3Si2 with FeCrAl via diffusion couple studies" Lingfeng He, Jason M. Harp, Rita E. Hoggan, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.10.057 | |
"Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: Investigating Pd as a metallic fuel additive" Lingfeng He, James A. King, Robert D. Mariani, Michael T. Benson, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.02.012 | |
"Hydrothermal synthesis of silicon oxide clad uranium oxide nanowires"
Jason M. Harp, Adrian R. Wagner, Rita E. Hoggan, Kevin R. Tolman, Lingfeng He,
[2018]
Journal of the American Ceramic Society
· DOI: 10.1111/jace.15295
A facile method to synthesize silicon oxide clad uranium oxide nanowires is presented. U3Si2, used as a precursor, was oxidized to produce uranium oxide nanocrystallites and amorphous silicon oxide under hydrothermal conditions at 300°C and a pressure of 7.8 × 106 Pa. The growth of uranium oxide nanowires was assisted by silicon oxide via assembling the uranium oxide nanocrystallites in an amorphous silicon oxide matrix. The microstructure and composition of silicon oxide clad uranium oxide nanowires were characterized by XRD, SEM, TEM, and EDS. The uranium oxide in the nanowires was determined as UO2.34 with a fluoride cubic structure. |
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"Radiation-induced grain subdivision and bubble formation in U3Si2 at LWR temperature" Bowen Gong, Lingfeng He, Jason Harp, Michael Tonks, Jie Lian, Tiankai Yao, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.10.027 | |
"Bubble evolution in Kr-irradiated UO2 during annealing" X.M. Bai, J. Pakarinen, B.J. Jaques, J. Gan, A.T. Nelson, A. El-Azab, T.R. Allen, L. He, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.09.036 | |
"Strength improvement and purification of Yb2Si2O7‐SiC nanocomposites by surface oxidation treatment"
Tadachika Nakayama, Hisayuki Suematsu, Tsuneo Suzuki, Lingfeng He, Hong‐Baek Cho, Koichi Niihara, Son T. Nguyen,
[2017]
Journal of the American Ceramic Society
· DOI: 10.1111/jace.14831
A two‐step processing was developed to prepare Yb2Si2O7‐SiC nanocomposites. Yb2Si2O7‐Yb2SiO5‐SiC composites were first fabricated by a solid‐state reaction/hot‐pressing method. The composites were then annealed at 1250°C in air for 2 hours to activate the oxidation of SiC, which effectively transformed the Yb2SiO5into Yb2Si2O7. The surface cracks purposely induced can be fully healed during the oxidation treatment. The treated composites have improved flexural strength compared to their pristine composites. The mechanism for crack healing and silicate transformation have been proposed and discussed in detail. |
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"Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C" Jason M. Harp, Rita E. Hoggan, Adrian R. Wagner, Lingfeng He, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.01.035 | |
"Effects of neutron irradiation of Ti3SiC2 and Ti3AlC2 in the 121–1085°C temperature range" Lingfeng He, Jian Gan, El'ad N. Caspi, Elizabeth N. Hoffman, Michel W. Barsoum, Darin J. Tallman, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.11.016 | |
"Irradiation Effects in Generation IV Nuclear Reactor Materials" L. He, H. Wen, B. Miller, X.M. Bai, T. Allen, A. Aitkaliyeva, [2016] · DOI: 10.1016/b978-0-08-100906-2.00007-0 | |
"Corrosion-induced microstructural developments in 316 stainless steel during exposure to molten Li2BeF4 (FLiBe) salt" Lingfeng He, David Carpenter, Kumar Sridharan, Guiqiu Zheng, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.10.023 · EID: 2-s2.0-84992143288 | |
"Corrosion-induced microstructural developments in 316 stainless steel during exposure to molten Li |
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"Effect of neutron irradiation on defect evolution in Ti3SiC2 and Ti2AlC" Lingfeng He, Brenda L. Garcia-Diaz, Elizabeth N. Hoffman, Gordon Kohse, Robert L. Sindelar, Michel W. Barsoum, Darin J. Tallman, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.10.030 · EID: 2-s2.0-84948445492 | |
"Effect of neutron irradiation on defect evolution in Ti |
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"Subsurface imaging of grain microstructure using picosecond ultrasonics" J. Pakarinen, L. He, H.B. Henderson, M.V. Manuel, A.T. Nelson, B.J. Jaques, D.P. Butt, D.H. Hurley, M. Khafizov, [2016] Acta Materialia · DOI: 10.1016/j.actamat.2016.04.003 · EID: 2-s2.0-84964328395 | |
"Inert Gas Measurement of Single Bubble in CeO2" Janne Pakarinen, Xianming Bai, Jian Gan, Yongqiang Wang, Anter El-Azab, Todd R. Allen, Lingfeng He, [2015] Microsc. Microanal. · DOI: 10.1017/s1431927615004559 | |
"Annealing-induced lattice recovery in room-temperature xenon irradiated CeO2: X-ray diffraction and electron energy loss spectroscopy experiments" Lingfeng He, Abdel-Rahman Hassan, Yongqiang Wang, Mahima Gupta, Anter El-Azab, Todd R. Allen, Janne Pakarinen, [2015] Journal of Materials Research · DOI: 10.1557/jmr.2015.13 · EID: 2-s2.0-84929707243 | |
"Annealing-induced lattice recovery in room-temperature xenon irradiated CeO<inf>2</inf>: X-ray diffraction and electron energy loss spectroscopy experiments" Lingfeng He, Abdel-Rahman Hassan, Yongqiang Wang, Mahima Gupta, Anter El-Azab, Todd R. Allen, Janne Pakarinen, [2015] Journal of Materials Research · DOI: 10.1557/jmr.2015.13 · EID: 2-s2.0-84929707243 | |
"Bubble formation and Kr distribution in Kr-irradiated UO2" 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, T.R. Allen, L.F. He, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.09.026 · EID: 2-s2.0-84908031776 | |
"Bubble formation and Kr distribution in Kr-irradiated UO |
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"High-Temperature corrosion of UNS N10003 in Molten Li2BeF4 (FLiBe) Salt"
Brian Kelleher, Lingfeng He, Guoping Cao, Mark Anderson, Todd Allen, Kumar Sridharan, Guiqiu Zheng,
[2015]
Corrosion
· DOI: 10.5006/1657
· EID: 2-s2.0-84942913529
Corrosion testing of UNS N10003 in molten fluoride salt was performed in purified molten 27LiF-BeF2 (66–34 mol%) (FLiBe) salt at 700°C for 1,000 h, in pure nickel and graphite capsules. In the nickel capsule tests, the near-surface region of the alloy exhibited an approximately 200 nm porous structure, an approximately 3.5 μm chromium-depleted region, and MoSi2 precipitates. In the tests performed in graphite capsules, the alloy samples gained weight because of the formation of a variety of Cr3C2, Cr7C3, Mo2C, and Cr23C6 carbide phases on the surface and in the subsurface regions of the alloy. A Cr-depleted region was observed in the near-surface region where Mo thermally diffused toward either the surface or the grain boundary, which induced an approximately 1.4 μm Ni3Fe alloy layer in this region. The carbide-containing layer extended to approximately 7 μm underneath the Ni3Fe layer. The presence of graphite dramatically changes the mechanisms of corrosion attack in UNS N10003 in molten FLiBe salt. In terms of the depth of attack, graphite clearly accelerates the corrosion, but the results appear to indicate that the formation of the Cr23C6 phase might stabilize the Cr and mitigate its dissolution in molten FLiBe salt. Moreover, a thermal diffusion controlled corrosion model that was fundamentally derived from Fick's second law was applied to predict the corrosion attack depth of 17.2 μm/y for UNS N10003 in molten FLiBe in the pure nickel capsule at 700°C. |
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"2.6 MeV proton irradiation effects on the surface integrity of depleted UO2" L. He, M. Gupta, J. Gan, A. Nelson, A. El-Azab, T.R. Allen, J. Pakarinen, [2014] Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms · DOI: 10.1016/j.nimb.2013.11.014 · EID: 2-s2.0-84890011923 | |
"2.6 MeV proton irradiation effects on the surface integrity of depleted UO |
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"Corrosion behavior of an alumina forming austenitic steel exposed to supercritical carbon dioxide" Paul Roman, Bin Leng, Kumar Sridharan, Mark Anderson, Todd R. Allen, Ling-Feng He, [2014] Corrosion Science · DOI: 10.1016/j.corsci.2013.12.023 · EID: 2-s2.0-84894736865 | |
"Developing yttria-based ceramics having high liquid metal corrosion resistance" [2014] Ceramic Transactions · EID: 2-s2.0-84908214876 | |
"Effect of Grain Boundaries on Krypton Segregation Behavior in Irradiated Uranium Dioxide" Lingfeng He, Hunter B. Henderson, Janne Pakarinen, Brian Jaques, Jian Gan, Darryl P. Butt, Todd R. Allen, Michele V. Manuel, Billy Valderrama, [2014] JOM · DOI: 10.1007/s11837-014-1182-x · EID: 2-s2.0-84911981510 | |
"In Situ TEM Observation of Dislocation Evolution in Polycrystalline UO2" M. Gupta, M. A. Kirk, J. Pakarinen, J. Gan, T. R. Allen, L. F. He, [2014] JOM · DOI: 10.1007/s11837-014-1186-6 · EID: 2-s2.0-84911965785 | |
"In Situ TEM Observation of Dislocation Evolution in Polycrystalline UO |
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"Microstructure changes and thermal conductivity reduction in UO2 following 3.9 MeV He2+ ion irradiation" Marat Khafizov, Lingfeng He, Chris Wetteland, Jian Gan, Andrew T. Nelson, David H. Hurley, Anter El-Azab, Todd R. Allen, Janne Pakarinen, [2014] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.07.053 · EID: 2-s2.0-84906833199 | |
"Microstructure changes and thermal conductivity reduction in UO |
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"Microstructure evolution in Xe-irradiated UO2 at room temperature" J. Pakarinen, M.A. Kirk, J. Gan, A.T. Nelson, X.-M. Bai, A. El-Azab, T.R. Allen, L.F. He, [2014] Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms · DOI: 10.1016/j.nimb.2014.03.018 · EID: 2-s2.0-84899120066 | |
"Microstructure evolution in Xe-irradiated UO |
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"Synthesis of BN nanosheet/nanotube-Fe nanocomposites by pulsed wire discharge and high-temperature annealing" J. Shirahata, H. Suematsu, T. Nakayama, T. Suzuki, W. Jiang, K. Niihara, L.F. He, [2014] Materials Letters · DOI: 10.1016/j.matlet.2013.12.008 · EID: 2-s2.0-84890959203 | |
"Thermal conductivity in nanocrystalline ceria thin films"
In‐Wook Park, Aleksandr Chernatynskiy, Lingfeng He, Jianliang Lin, John J. Moore, David Swank, Thomas Lillo, Simon R. Phillpot, Anter El‐Azab, David H. Hurley, Marat Khafizov,
[2014]
Journal of the American Ceramic Society
· DOI: 10.1111/jace.12673
· EID: 2-s2.0-84893977235
The thermal conductivity of nanocrystalline ceria films grown by unbalanced magnetron sputtering is determined as a function of temperature using laser‐based modulated thermoreflectance. The films exhibit significantly reduced conductivity compared with stoichiometric bulk |
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"Fission Products in Nuclear Fuel: Comparison of Simulated Distribution with Correlative Characterization Techniques"
H.B. Henderson, L. He, C. Yablinsky, J. Gan, A.-R. Hassan, A. El-Azab, T.R. Allen, M.V. Manuel, B. Valderrama,
[2013]
· DOI: 10.1017/s1431927613006831
Extended abstract of a paper presented at Microscopy and Microanalysis 2013 in Indianapolis, Indiana, USA, August 4 – August 8, 2013. |
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"In situ TEM observation of dislocation evolution in Kr-irradiated UO 2 single crystal" Mahima Gupta, Clarissa A. Yablinsky, Jian Gan, Marquis A. Kirk, Xian-Ming Bai, Janne Pakarinen, Todd R. Allen, Ling-Feng He, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2013.06.050 | |
"Synthesis and structure-property relationships of a new family of layered carbides in Zr-Al(Si)-C and Hf-Al(Si)-C systems" Ling-Feng He, Zhi-Jun Lin, Jing-Yang Wang, Yan-Chun Zhou, [2013] Journal of the European Ceramic Society · DOI: 10.1016/j.jeurceramsoc.2013.05.020 | |
"Transmission electron microscopy investigation of krypton bubbles in polycrystalline CeO2" [2013] Nuclear Technology · EID: 2-s2.0-84879071544 | |
"Effect of Ti dopant on the mechanical properties and oxidation behavior of Zr 2[Al(Si)] 4C 5 ceramics" Huimin Xiang, Ling-Feng He, Luchao Sun, Yanchun Zhou, Xinpo Lu, [2011] Journal of the American Ceramic Society · DOI: 10.1111/j.1551-2916.2010.04300.x | |
"Fabrication and characterization of tricalcium silicate bioceramics with high mechanical properties by spark plasma sintering" Lianjun Wang, Lingfeng He, Wan Jiang, Wanyin Zhai, Kaili Lin, Lidong Chen, Jiang Chang, Hongbin Zhong, [2011] International Journal of Applied Ceramic Technology · DOI: 10.1111/j.1744-7402.2011.02613.x | |
"Mechanical properties and bioactivity of β-Ca 2SiO 4 ceramics synthesized by spark plasma sintering" Lianjun Wang, Yuchi Fan, Lingfeng He, Kali Lin, Wan Jiang, Jiang Chang, Lidong Chen, Hongbin Zhong, [2011] Ceramics International · DOI: 10.1016/j.ceramint.2011.03.037 | |
"Mechanical properties of Y2Ti2O7" J. Shirahata, T. Nakayama, T. Suzuki, H. Suematsu, I. Ihara, Y.W. Bao, T. Komatsu, K. Niihara, L.F. He, [2011] Scripta Materialia · DOI: 10.1016/j.scriptamat.2010.11.042 | |
"A new method to improve the high-temperature mechanical properties of Ti3SiC2 by substituting Ti with Zr, Hf, or Nb"
Ling‐Feng He, Li‐Li Zheng, Jie Zhang, Yi‐Wang Bao, Yan‐Chun Zhou, De‐Tian Wan,
[2010]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2010.03637.x
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"Crystal structure and theoretical elastic property of a new ternary ceramic HfAl4C4"
Lingfeng He, Fangzhi Li, Jingyang Wang, Yanchun Zhou, Hongqiang Nian,
[2010]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2009.03543.x
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"In situ reaction synthesis and mechanical properties of TaC-TaSi 2 composites"
Lingfeng He, Fangzhi Li, Ling Wu, Jingyang Wang, Meishuan Li, YiWang Bao, Yanchun Zhou, Lingfeng He, Fangzhi Li, Ling Wu, Chunfeng Hu,
[2010]
International Journal of Applied Ceramic Technology
· DOI: 10.1111/j.1744-7402.2009.02392.x
TaC–TaSi2 composites were fabricated at 1700°C by an |
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"Mechanical and thermal properties of a Hf2[Al(Si)]4C5 ceramic prepared by in situ reaction/hot-pressing" H.Q. Nian, X.P. Lu, Y.W. Bao, Y.C. Zhou, L.F. He, [2010] Scripta Materialia · DOI: 10.1016/j.scriptamat.2009.12.020 | |
"Mechanisms and kinetics of the hydrothermal oxidation of bulk titanium silicon carbide"
Volker Presser, Christoph Berthold, Klaus Georg Nickel, Xin Wang, Christoph Raisch, Thomas Chassé, Lingfeng He, Yanchun Zhou, Haibin Zhang,
[2010]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2009.03570.x
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"Microstructure, mechanical, thermal, and oxidation properties of a Zr2[Al(Si)]4C5-SiC composite prepared by in situ reaction/hot-pressing" Fang-Zhi Li, Xin-Po Lu, Yi-Wang Bao, Yan-Chun Zhou, Ling-Feng He, [2010] Journal of the European Ceramic Society · DOI: 10.1016/j.jeurceramsoc.2010.02.005 | |
"Oxidation behavior of ternary carbide ceramics in Hf-Al-C system in air"
Jing‐Jing Li, Hong‐Qiang Nian, Xiao‐Hui Wang, Yi‐Wang Bao, Mei‐Shuan Li, Jing‐Yang Wang, Yan‐Chun Zhou, Ling‐Feng He,
[2010]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2010.03891.x
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"Reciprocating friction and wear behavior of Zr2[Al(Si)] 4C5 and Zr2[Al(Si)]4C 5-SiC composite against Si3N4 ball"
Ling‐Feng He, Ji‐Xin Chen, Xin‐Po Lu, Yan‐Chun Zhou, Ling Wu,
[2010]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2010.03718.x
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"Surface strengthening of Ti3SiC2 through magnetron sputtering of Mo and Zr and subsequent annealing" Aijun Li, Jie Zhang, Lingfeng He, Yanchun Zhou, Haiping Guo, [2010] Journal of the European Ceramic Society · DOI: 10.1016/j.jeurceramsoc.2009.04.042 | |
"High-temperature internal friction, stiffness and strength of Zr-Al(Si)-C ceramics" X.P. Lu, Y.W. Bao, J.Y. Wang, Y.C. Zhou, L.F. He, [2009] Scripta Materialia · DOI: 10.1016/j.scriptamat.2009.03.004 | |
"Highly conductive and strengthened copper matrix composite reinforced by Zr2Al3C4 particulates" Lingfeng He, Yanchun Zhou, Jie Zhang, [2009] Scripta Materialia · DOI: 10.1016/j.scriptamat.2009.02.026 | |
"Mechanical and thermophysical properties of Zr-Al-Si-C ceramics"
Yi‐Wang Bao, Jing‐Yang Wang, Mei‐Shuan Li, Yan‐Chun Zhou, Ling‐Feng He,
[2009]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2008.02879.x
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"Microstructure and mechanical and thermal properties of ternary carbides in Hf-Al-C system" Y.W. Bao, J.Y. Wang, M.S. Li, Y.C. Zhou, L.F. He, [2009] Acta Materialia · DOI: 10.1016/j.actamat.2009.02.027 | |
"Tribological properties of a Zr2Al3C4 ceramic at ambient temperature"
Ling‐Feng He, Yi‐Wang Bao, Yan‐Chun Zhou, Ling Wu,
[2009]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2008.02805.x
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"Ultrahigh-temperature oxidation of Zr2Al3C4 via rapid induction heating" H.B. Zhong, J.J. Xu, M.S. Li, Y.W. Bao, J.Y. Wang, Y.C. Zhou, L.F. He, [2009] Scripta Materialia · DOI: 10.1016/j.scriptamat.2008.12.002 | |
"Zirconium aluminum carbides: New precursors for synthesizing ZrO 2-Al2O3 composites"
Yi‐Wang Bao, Yan‐Chun Zhou, Ling‐Feng He,
[2009]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2009.03281.x
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"Atomic-scale microstructure and elastic properties of quaternary Zr-Al-Si-C ceramics" L.F. He, J.Y. Wang, M.S. Li, Y.W. Bao, Y.C. Zhou, Z.J. Lin, [2008] Acta Materialia · DOI: 10.1016/j.actamat.2007.12.055 | |
"Crystal structure and theoretical elastic property of two new ternary ceramics Hf3Al4C6 and Hf2Al4C5" Z.J. Lin, J.Y. Wang, Y.W. Bao, Y.C. Zhou, L.F. He, [2008] Scripta Materialia · DOI: 10.1016/j.scriptamat.2007.12.002 | |
"Improving the high-temperature oxidation resistance of Zr2 Al3C4 by silicon pack cementation"
Y.W. Bao, M.S. Li, J.Y. Wang, Y.C. Zhou, L.F. He,
[2008]
Journal of Materials Research
· DOI: 10.1557/jmr.2008.0285
Silicon pack cementation has been applied to improve the oxidation resistance of Zr2Al3C4. The Si pack coating is mainly composed of an inner layer of ZrSi2 and SiC and an outer layer of Al2O3 at 1200 °C. The growth kinetics of silicide coating at 1000–1200 °C obey a parabolic law with an activation energy of 110.3 ± 16.7 kJ/mol, which is controlled by inward diffusion of Si and outward diffusion of Al. Compared with Zr2Al3C4, the oxidation resistance of siliconized Zr2Al3C4 is greatly improved due to the formation of protective oxidation products, aluminosilicate glass, mullite, and ZrSiO4. |
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"In situ reaction synthesis and mechanical properties of V2AlC"
Lingfeng He, Mingyue Liu, Xiaohui Wang, Jingyang Wang, Meishuan Li, Yiwang Bao, Yanchun Zhou, Chunfeng Hu,
[2008]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2008.02774.x
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"Isothermal oxidation of bulk Zr2Al3C4 at 500 to 1000 °C in air"
Z.J. Lin, Y.W. Bao, M.S. Li, J.Y. Wang, Y.C. Zhou, L.F. He,
[2008]
Journal of Materials Research
· DOI: 10.1557/jmr.2008.0042
The isothermal oxidation behavior of Zr2Al3C4 in the temperature range of 500 to 1000 °C for 20 h in air has been investigated. The oxidation kinetics follow a parabolic law at 600 to 800 °C and a linear law at higher temperatures. The activation energy is determined to be 167.4 and 201.2 kJ/mol at parabolic and linear stages, respectively. The oxide scales have a monolayer structure, which is a mixture of ZrO2 and Al2O3. As indicated by x-ray diffraction and Raman spectra, the scales formed at 500 to 700 °C are amorphous, and at higher temperatures are α-Al2O3 and t-ZrO2 nanocrystallites. The nonselective oxidation of Zr2Al3C4 can be attributed to the strong coupling between Al3C2 units and ZrC blocks in its structure, and the close oxygen affinity of Zr and Al. |
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"Microstructure and properties of bulk Ta2AlC ceramic synthesized by an in situ reaction/hot pressing method" Lingfeng He, Jie Zhang, Yiwang Bao, Jingyang Wang, Meishuan Li, Yanchun Zhou, Chunfeng Hu, [2008] Journal of the European Ceramic Society · DOI: 10.1016/j.jeurceramsoc.2007.10.006 | |
"Oxidation of Zr2[Al(Si)]4C5 and Zr3[Al (Si)]4C6 in air"
Y.W. Bao, M.S. Li, J.Y. Wang, Y.C. Zhou, L.F. He,
[2008]
Journal of Materials Research
· DOI: 10.1557/jmr.2008.0411
The oxidation behavior of Zr2[Al(Si)]4C5 and Zr3[Al(Si)]4C6 in air has been investigated. The oxidation kinetics of bulk Zr2[Al(Si)]4C5 and Zr3[Al(Si)]4C6 at 900–1300 °C generally follow a parabolic law at a very short initial stage and then a linear law for a long period with the activation energy of 237.9 and 226.8 kJ/mol, respectively. The oxide scales have a duplex structure, consisting of mainly an outer porous layer of ZrO2, Al2O3, and aluminosilicate/mullite, and a thin inner compact layer of these oxides plus remaining carbon. The oxidation resistance of Zr2[Al(Si)]4C5 and Zr3[Al(Si)]4C6 has been improved compared with Zr2Al3C4, and is much better than ZrC due to larger fraction of protective oxidation products, Al2O3 and aluminosilicate/mullite. |
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"Synthesis, Microstructure, and Mechanical Properties of Al3BC3"
Fangzhi Li, Lingfeng He, Mingyue Liu, Jie Zhang, Jiemin Wang, Yiwang Bao, Jingyang Wang, Yanchun Zhou, Chunfeng Hu,
[2008]
· DOI: 10.1111/j.1551-2916.2008.02424.x
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"In-Situ Reaction Synthesis, Electrical, Thermal, and Mechanical Properties of Nb4AlC3"
Fangzhi Li, Lingfeng He, Mingyue Liu, Jie Zhang, Jiemin Wang, Yiwang Bao, Jingyang Wang, Yanchun Zhou, Chunfeng Hu,
[2008]
· DOI: 10.1111/j.1551-2916.2008.02424.x
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"Elastic and thermal properties of Zr2 Al3 C4: Experimental investigations and ab initio calculations"
J. Y. Wang, Y. W. Bao, Y. C. Zhou, L. F. He,
[2007]
Journal of Applied Physics
· DOI: 10.1063/1.2773679
This article presents the results of combined experimental and theoretical studies of elastic and thermal properties of Zr2Al3C4 carbide. The full set of second order elastic constants, bulk modulus, shear modulus, and Young’s modulus of Zr2Al3C4 were calculated and compared with those of Zr3Al3C5 and ZrC. The experimentally measured Young’s modulus and shear modulus are in good agreement with theoretical ones. The calculated Debye temperature from elastic constants of Zr2Al3C4 is 830 K, which is slightly higher than that of Zr3Al3C5, and exhibits pronounced enhancement in comparison with that of ZrC. The highest Debye temperature of Zr2Al3C4 is related with its highest specific stiffness, i.e., the stiffness-to-weight ratio. The heat capacity and thermal conductivity of Zr2Al3C4 were measured by means of the flash method. The thermal conductivity of Zr2Al3C4 decreases with increasing temperature, for instance the values at room temperature and 1600 K are 15.5 and 10.1 W/m K, respectively. The investigations provide information on elastic and thermal properties of Zr2Al3C4 with promising high temperature applications. |
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"In situ synthesis and properties of Ti 3AlC 2/TiB 2 composites"
Meishuan Li, Yanchun Zhou, Jie Zhang, Lingfeng He, Chao Li,
[2007]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2007.01954.x
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"Layered stacking characteristics of ternary zirconium aluminum carbides"
L.F. He, M.S. Li, J.Y. Wang, Y.C. Zhou, Z.J. Lin,
[2007]
Journal of Materials Research
· DOI: 10.1557/jmr.2007.0409
Layered stacking characteristics of ternary Zr–Al–C carbides were investigated using scanning transmission electron microscopy (STEM). Three previously unknown compounds, i.e., Zr4Al3C6, Zr5Al6C9, and Zr7Al6C11 were identified. The present study extends the structural information of ternary Zr–Al–C ceramics. The influence of the thickness of the NaCl-type Zr-C slab on the elastic properties of ternary Zr–Al–C ceramics is discussed based on first-principles calculations. In addition, direct atomic-resolution observations illustrate the process for forming the unique layered crystal structures of ternary Zr–Al–C ceramics. These results also provide insights into the formation mechanism of layered ternary Zr–Al–C carbides. |
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"Physical and mechanical properties of bulk Ta4AlC3 ceramic prepared by an in situ reaction synthesis/hot-pressing method"
Zhijun Lin, Lingfeng He, Yiwang Bao, Jingyang Wang, Meishuan Li, Yanchun Zhou, Chunfeng Hu,
[2007]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2007.01804.x
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"Synthesis and characterization of bulk Zr2Al3C 4 ceramic"
Zhijun Lin, Jingyang Wang, Yiwang Bao, Meishuan Li, Yanchun Zhou, Lingfeng He,
[2007]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2007.01964.x
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"Synthesis and oxidation of Zr3Al3C5 powders" [2007] International Journal of Materials Research · EID: 2-s2.0-33847074954 | |
"Synthesis and oxidation of Zr |
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"Synthesis, physical, and mechanical properties of bulk Zr 3Al3C5 ceramic"
Yanchun Zhou, Yiwang Bao, Zhijun Lin, Jingyang Wang, Lingfeng He,
[2007]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2007.01518.x
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"Atomic-scale microstructures of Zr2Al3C4 and Zr3Al3C5 ceramics" M.J. Zhuo, L.F. He, Y.C. Zhou, M.S. Li, J.Y. Wang, Z.J. Lin, [2006] Acta Materialia · DOI: 10.1016/j.actamat.2006.02.052 | |
"First-principles prediction of the mechanical properties and electronic structure of ternary aluminum carbide Zr3 Al3 C5" Yanchun Zhou, Zhijun Lin, Ting Liao, Ling Feng He, Jingyang Wang, [2006] Physical Review B - Condensed Matter and Materials Physics · DOI: 10.1103/physrevb.73.134107 | |
Source: ORCID/CrossRef using DOI |
This NSUF Profile is 70
Top 5% of all NSUF-supported publication authors
Presented an NSUF-supported publication
Submitted 3+ RTE Proposals to NSUF
Top 5% of all RTE Proposals awarded
Top 5% of all RTE Proposal collaborations
Top 5% of all RTE Proposals reviewed
Radiation Effects of High Entropy Alloys - FY 2024 CINR, #24-31410
In situ irradiation of uranium carbide - FY 2023 RTE 2nd Call, #23-4721
In situ irradiation of fission nanoprecipitates - FY 2022 RTE 1st Call, #22-4461
Microstructural characterization of transmutation nitride fuels for fast reactors - FY 2018 RTE 2nd Call, #18-1428
Characterization of grain boundaries of Alloy X-750 irradiated in EBR-II - FY 2018 RTE 1st Call, #18-1254
Investigation of gas bubble behavior under ion irradiation - FY 2017 RTE 2nd Call, #17-912
In Situ Observation of Lunar Crater Features in Xe Irradiated UO2 at High Dose - FY 2016 RTE 2nd Call, #16-657
Transmission Electron Microscopy Study of the Microstructure Evolution in Kr Irradiated UO2 - FY 2014 RTE 2nd Call, #12-483
Study of the Microstructure of Kr and Xe Irradiated UO2 by Advanced Microscopy Techniques - FY 2013 RTE Solicitation, #13-431
Study of the Microstructure of Irradiated CeO2 by Advanced Microscopy Techniques - FY 2011 RTE Solicitation, #11-327
Self-Alpha Irradiation of UO2-UB2 fuel - FY 2024 RTE 2nd Call, #24-5002
In-situ irradiation of ZrC and ZrN above 800 C - FY 2024 RTE 1st Call, #24-4892
In situ irradiation of spent nuclear fuels - FY 2023 RTE 3rd Call, #23-4771
Atom probe and transmission electron microscopy studies on neutron irradiated FeCrMnNi Compositionally Complex Alloy - FY 2022 RTE 1st Call, #22-4459
Dislocation loop and bubble evolution in helium irradiated ThO2 and UO2 single crystals - FY 2022 RTE 1st Call, #22-4442
The effects of stress on void superlattice formation during Cr+ self-ion-irradiation of chromium - FY 2021 RTE 1st Call, #21-4320
ChemisSTEM Characterization of Bulk Heavy Ion Irradiated Complex Concentrated Alloys - FY 2020 RTE 2nd Call, #20-4095
UCl4/UCl3 speciation - FY 2020 RTE 2nd Call, #20-3084
Microstructure characterization of 6Li(n,a)3H reaction damage sapphire claddings - FY 2020 RTE 1st Call, #20-3018
In-situ Micro-tensile Testing for Measuring Grain Boundary Strength of NiCr Alloys under Simultaneous Irradiation and Corrosion Environments - FY 2020 RTE 1st Call, #20-3028
Ion Irradiation and TEM Characterization of Polymer Derived C-SiC-SiOC Nanocomposites - FY 2020 RTE 1st Call, #20-3004
Investigation of fission gas bubble distribution, phase transformations, and bubble growth kinetics in a FFTF-irradiated U-10Zr fuel - FY 2019 RTE 3rd Call, #19-2899
Understand the Fission Products Behavior in UCO Fuel Kernels of safety tested AGR2 TRISO Fuel Particles by Using Titan Themis 200 with ChemiSTEM Capability - FY 2019 RTE 3rd Call, #19-2893
High resolution (S)TEM/EDS characterization of neutron irradiated commercial Zr-Nb alloys - FY 2019 RTE 3rd Call, #19-2860
Advanced microstructural characterization of irradiation-induced phase transformation in 304 steel - FY 2019 RTE 3rd Call, #19-2858
The influence of proton irradiation damage on the corrosion of Hastelloy N exposed to FliNaK molten salt - FY 2019 RTE 3rd Call, #19-2833
EPMA and TEM Characterization of a UO2 fuel pellet and cladding interaction layer - FY 2019 RTE 2nd Call, #19-1796
Microstructural characterizations of in-core molten salt irradiated TRISO particles - FY 2019 RTE 2nd Call, #19-1785
Irradiation and TEM Characterization of induced Defects in a-U and d-UZr2+x Crystals - FY 2019 RTE 2nd Call, #19-1784
Understand the atomic positions of the metallic fission product in UCO Fuel Kernels and Determine the exact stoichiometry of UC, UO phase of Irradiated TRISO Fuel Particles by Using Titan Themis 200 with EELS characterization Capability - FY 2019 RTE 2nd Call, #19-1779
Investigation of the mechanism behind irradiation-decelerated corrosion of Ni-20Cr in molten fluoride salt - FY 2019 RTE 2nd Call, #19-1742
In-situ separate effect studies of thermal and radiation effects on Xe diffusion in alpha-U and U-10Zr. - FY 2019 RTE 1st Call, #19-1621
Ion irradiation of ThO2 and UO2 single crystals - FY 2019 RTE 1st Call, #19-1663
Nanoindentation of Phases in Irradiated and Control U-10Zr Fuels - FY 2019 RTE 1st Call, #19-1666
Thermal Driven Grain Growth and Fission Gas Bubble Coarsening in Nano-grain Sized U3Si2 - FY 2019 RTE 1st Call, #19-1691
Grain Size Effects on He and Xe behavior in UO2 and ThO2 - FY 2018 RTE 3rd Call, #18-1561
Microstructural characterization of grain boundaries in Hastelloy N corroded in molten FLiBe salt under neutron irradiation - FY 2018 RTE 3rd Call, #18-1545
Electron microscopy characterization of fast reactor MOX joint oxyde-gaine (JOG) - FY 2018 RTE 3rd Call, #18-1538
TEM/EDS study of Nb redistribution in ZrNb alloys following proton irradiation - FY 2018 RTE 2nd Call, #18-1392
TEM and APT Characterization of Ion-Irradiated High-Entropy Alloys for Sodium-Cooled Fast Reactors - FY 2018 RTE 2nd Call, #18-1380
Characterization of Neutron-Irradiated Zr-1Nb-O Using Scanning Transmission Electron Microscopy - FY 2018 RTE 2nd Call, #18-1374
Understand the Fission Products Behavior and Irradiation Effects in UCO Fuel Kernels of Irradiated AGR-1 and AGR-2 TRISO Fuel Particles Using Titan Themis 200 with ChemiSTEM Capability - FY 2018 RTE 1st Call, #18-1257
Understanding the role of grain boundary character in segregation behavior of solute elements in neutron irradiated 304 SS using Atom Probe Tomography. - FY 2018 RTE 1st Call, #18-1253
Investigation of gas bubble behavior in metals using in-situ Ne, Ar and Kr ion irradiation - FY 2018 RTE 1st Call, #18-1213
Electron Tomography for Three-Dimensional Characterization of Intragranular Fission Product Transport in Neutron-Irradiated Silicon Carbide in TRISO Fuel - FY 2018 RTE 1st Call, #18-1151
APT and TEM study of redistribution of alloying elements in ZrNb alloys following proton irradiation: effects on in-reactor corrosion kinetics. - FY 2017 RTE 3rd Call, #17-1001
Fission Gas Behavior and Fuel Swelling of Accident Tolerant U3Si2 Fuels by Ion Beam Irradiation - FY 2017 RTE 2nd Call, #17-957
The window of gas-bubble superlattice formation in bcc metals - FY 2017 RTE 1st Call, #16-846
Radiation Response and Microstructure of Accident Tolerant U3Si2 Fuels by Ion Beam Irradiation - FY 2017 RTE 1st Call, #16-835
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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