Jian Gan

Profile Information
Name
Dr. Jian Gan
Institution
Idaho National Laboratory
Position
Research Scientist
Affiliation
Idaho National Laboratory
h-Index
ORCID
0000-0002-9121-4164
Expertise
Ion-Irradiation, Nuclear Fuel, Radiation Damage
Publications:
"2.6 MeV proton irradiation effects on the surface integrity of depleted UO2" Todd Allen, Anter EL-AZAB, Jian Gan, Mahima Gupta, Andrew Nelson, Janne Pakarinen, Nuclear Instruments and Methods B Vol. 319 2014 100-106 Link
The effect of low temperature proton irradiation in depleted uranium dioxide was examined as a function of fluence. With 2.6 MeV protons, the fluence limit for preserving a good surface quality was found to be relatively low, about 1.4 and 7.0 × 1017 protons/cm2 for single and poly crystalline samples, respectively. Upon increasing the fluence above this threshold, severe surface flaking and disintegration of samples was observed. Based on scanning electron microscopy (SEM) and X-ray diffraction (XRD) observations the causes of surface failure were associated to high H atomic percent at the peak damage region due to low solubility of H in UO2. The resulting lattice stress is believed to exceed the fracture stress of the crystal at the observed fluencies. The oxygen point defects from the displacement damage may hinder the H diffusion and further increase the lattice stress, especially at the peak damage region.
"A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT)" Mukesh Bachhav, Jian Gan, Dennis Keiser, Jeffrey Giglio, Daniel Jadernas, Ann Leenaers, Sven Van den Berghe, Journal of Nuclear Materials Vol. 528 2020 Link
"Atom probe study of irradiation-enhanced a' precipitation in neutron-irradiated Fe–Cr model alloys" Wei-Ying Chen, Jian Gan, Stuart Maloy, Kun Mo, Maria Okuniewski, James Stubbins, Yinbin Miao, Yaqiao Wu, Carolyn Tomchik, Journal of Nuclear Materials Vol. 462 2015 242-249 Link
Atom probe tomography (APT) was performed to study the effects of Cr concentrations, irradiation doses and irradiation temperatures on α′ phase formation in Fe–Cr model alloys (10–16 at.%) irradiated at 300 and 450 °C to 0.01, 0.1 and 1 dpa. For 1 dpa specimens, α′ precipitates with an average radius of 1.0–1.3 nm were observed. The precipitate density varied significantly from 1.1 × 1023 to 2.7 × 1024 1/m3, depending on Cr concentrations and irradiation temperatures. The volume fraction of α′ phase in 1 dpa specimens qualitatively agreed with the phase diagram prediction. For 0.01 dpa and 0.1 dpa, frequency distribution analysis detected slight Cr segregation in high-Cr specimens, but not in Fe–10Cr specimens. Proximity histogram analysis showed that the radial Cr concentration was highest at the center of α′ precipitates. For most precipitates, the Cr contents were significantly lower than that predicted by the phase diagram. The Cr concentration at precipitate center increased with increasing precipitate size.
"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.
"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.
"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.
"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.
"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.
"Fission Products in Nuclear Fuel: Comparison of Simulated Distribution with Correlative Characterization Techniques" Anter EL-AZAB, Jian Gan, Billy Valderrama, Clarissa Yablinsky, Microscopy and Microanalysis Vol. 19 2013 968-969 Link
During the fission process in a nuclear reactor, uranium dioxide (UO2) fuel material is irradiated, forming fission products (FPs). The addition of FPs alters the path phonons travel in UO2, detrimentally altering the thermal conductivity of the fuel. [1] To improve fuel performance, a fundamental understanding of the role of insoluble FPs, such as Xenon (Xe), during microstructural evolution is critical. Correlative characterization techniques where atom probe tomography (APT) is paired with transmission electron microscopy (TEM) can provide unique insights into the segregation behavior of FPs. Coupling these techniques with computer simulations of fission product distribution provide deeper understanding of FP migration during service. Although there are limitations with each of these techniques in isolation, significant insight into material behavior can be gained with the concurrent and synergistic pairing of multiple experimental and computational techniques.
"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.
"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.
"Influence of instrument conditions on the evaporation behavior of uranium dioxide with UV laser-assisted atom probe tomography" Jian Gan, Billy Valderrama, Hunter Henderson, Michele Manuel, Journal of Nuclear Materials Vol. 459 2015 37-43 Link
Atom probe tomography (APT) provides the ability to detect subnanometer chemical variations spatially, with high accuracy. However, it is known that compositional accuracy can be affected by experimental conditions. A study of the effect of laser energy, specimen base temperature, and detection rate is performed on the evaporation behavior of uranium dioxide (UO2). In laser-assisted mode, tip geometry and standing voltage also contribute to the evaporation behavior. In this investigation, it was determined that modifying the detection rate and temperature did not affect the evaporation behavior as significantly as laser energy. It was also determined that three laser evaporation regimes are present in UO2. Very low laser energy produces a behavior similar to DC-field evaporation, moderate laser energy produces the desired laser-assisted field evaporation characteristic and high laser energy induces thermal effects, negatively altering the evaporation behavior. The need for UO2 to be analyzed under moderate laser energies to produce accurate stoichiometry distinguishes it from other oxides. The following experimental conditions providing the best combination of mass resolving power, accurate stoichiometry, and uniform evaporation behavior: 50 K, 10 pJ laser energy, a detection rate of 0.003 atoms per pulse, and a 100 kHz repetition rate.
"In-Situ TEM Observation of Dislocation Evolution in Kr-Irradiated UO2 Single Crystal" Todd Allen, Jian Gan, Mahima Gupta, Janne Pakarinen, Clarissa Yablinsky, Marquis Kirk, Xianming Bai, Journal of Nuclear Materials Vol. 443 2013 71-77 Link
In situ transmission electron microscopy (TEM) observation of UO2 single crystal irradiated with Kr ions at high temperatures was conducted to understand the dislocation evolution due to high-energy radiation. The dislocation evolution in UO2 single crystal is shown to occur as nucleation and growth of dislocation loops at low-irradiation doses, followed by transformation to extended dislocation segments and networks at high doses, as well as shrinkage and annihilation of some loops and dislocations due to high temperature annealing. Generally the trends of dislocation evolution in UO2 were similar under Kr irradiation at different ion energies and temperatures (150 keV at 600 °C and 1 MeV at 800 °C) used in this work. Interstitial-type dislocation loops with Burgers vector along 〈1 1 0〉 were observed in the Kr-irradiated UO2. The irradiated specimens were denuded of dislocation loops near the surface.
"Investigation of material property influenced stoichiometric deviations as evidenced during UV laser-assisted atom probe tomography in fluorite oxides" Todd Allen, Jian Gan, Hunter Henderson, Michele Manuel, Billy Valderrama, Clarissa Yablinsky, Nuclear Instruments and Methods in Physics Research B: Beam Interactions with Materials and Atoms Vol. 359 2015 107-114 Link
Oxide materials are used in numerous applications such as thermal barrier coatings, nuclear fuels, and electrical conductors and sensors, all applications where nanometer-scale stoichiometric changes can affect functional properties. Atom probe tomography can be used to characterize the precise chemical distribution of individual species and spatially quantify the oxygen to metal ratio at the nanometer scale. However, atom probe analysis of oxides can be accompanied by measurement artifacts caused by laser-material interactions. In this investigation, two technologically relevant oxide materials with the same crystal structure and an anion to cation ratio of 2.00, pure cerium oxide (CeO2) and uranium oxide (UO2) are studied. It was determined that electronic structure, optical properties, heat transfer properties, and oxide stability strongly affect their evaporation behavior, thus altering their measured stoichiometry, with thermal conductance and thermodynamic stability being strong factors.
"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.
"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.
"Neutron irradiation effects in Fe and Fe-Cr at 300°C" Wei-Ying Chen, Yinbin Miao, Jian Gan, Maria Okuniewski, Stuart Maloy, James Stubbins, Acta Materialia Vol. 111 2016 407-416 Link
Fe and Fe-Cr (Cr = 10-16 at.%) specimens were neutron-irradiated at 300 °C to 0.01, 0.1 and 1 dpa. The TEM observations indicated that the Cr significantly reduced the mobility of dislocation loops and suppressed vacancy clustering, leading to distinct damage microstructures between Fe and Fe-Cr. Irradiation-induced dislocation loops in Fe were heterogeneously observed in the vicinity of grown-in dislocations, whereas the loop distribution observed in Fe-Cr is much more uniform. Voids were observed in the irradiated Fe samples, but not in irradiated Fe-Cr samples. Increasing Cr content in Fe-Cr results in a higher density, and a smaller size of irradiation-induced dislocation loops. Orowan mechanism was used to correlate the observed microstructure and hardening, which showed that the hardening in Fe-Cr can be attributed to the formation of dislocation loops and &#945;&#8242; precipitates.
"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
"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
"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.
"Transmission Electron Microscopy Investigation of Krypton Bubbles in Polycrystalline CeO2" Todd Allen, Jian Gan, Mahima Gupta, Clarissa Yablinsky, Marquis Kirk, Nuclear Technology Vol. 182 2013 164-169 Link
To gain an understanding of gas bubble transport in oxide nuclear fuel, this paper uses polycrystalline CeO2, composed of both nanograins and micrograins, as a surrogate material for UO2. The CeO2 was implanted with 150-keV Kr ions up to a dose of 1 &times; 1016 ions/cm2 at 600&deg;C. Transmission electron microscopy characterizations of small Kr bubbles in nanograin and micrograin regions were compared. The grain boundary acted as an efficient defect sink, as evidenced by smaller bubbles and a lower bubble density in the nanograin region as compared to the micrograin region.
Presentations:
"Atom probe analysis of a neutron irradiated Fe-14Cr model alloy" Jian Gan, Stuart Maloy, Yinbin Miao, Kun Mo, Yaqiao Wu, ICFRM 2013 January 1-9, (2013)
"Characterization of Oxide Fuel Surface Chemistry with Atom Probe Tomography" Anter EL-AZAB, Jian Gan, Hunter Henderson, Michele Manuel, Billy Valderrama, 2013 ANS Winter Meeting November 10-13, (2013)
"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)
"Damage Structure Evolution in Ion Irradiated UO2" Todd Allen, Jian Gan, Mahima Gupta, Andrew Nelson, Jeff Terry, TMS 2014 February 16-20, (2014)
"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)
"Kr and Xe Bubble Characterization in CeO2" Todd Allen, Jian Gan, Mahima Gupta, Janne Pakarinen, TMS 2014 February 16-20, (2014)
"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)
"Microstructure and Mechanical Property Studies on Neutron-Irradiated Ferritic FeCr Model Alloys" Jian Gan, Stuart Maloy, Yinbin Miao, Kun Mo, James Stubbins, Yaqiao Wu, TMS Annual Meeting February 16-20, (2014)
"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)
"Nano-scale Irradiation Induced Chemistry Changes in Oxide Fuel Materials" Todd Allen, Jian Gan, Hunter Henderson, Janne Pakarinen, Billy Valderrama, TMS 2014 February 16-20, (2014)
"Radiation Effects in UO2" Todd Allen, Jian Gan, Mahima Gupta, Michele Manuel, Andrew Nelson, Janne Pakarinen, Billy Valderrama, TMS 2014 February 16-20, (2014)
"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)
Additional Publications:
"In-situ irradiation of uranium carbide" Adrian R. Wagner, Laura Hawkins, Wei-Ying Chen, Jennifer K. Watkins, Jian Gan, Lingfeng He, Rashed Almasri, [2025] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2025.156082
"Revisiting point defect thermodynamics in group IVB and VB transition metal carbides" Larry K. Aagesen, Jian Gan, Chao Jiang, [2025] Computational Materials Science · DOI: 10.1016/j.commatsci.2025.114238
"Phase transformation mechanism in irradiation-induced superlattice formation" Yongfeng Zhang, Chao Jiang, Jian Gan, Larry K. Aagesen, [2025] Computational Materials Science · DOI: 10.1016/j.commatsci.2024.113418
"Effect of TiN coating on suppressing Ce-Fe interaction under irradiation" Chao Jiang, Yizhi Zhang, Yifan Zhang, Jiawei Song, Ke Xu, Benson Kunhung Tsai, Xuanyu Sheng, Haiyan Wang, Yinbin Miao, Peter Mouche, Kun Mo, Bei Ye, Jian Gan, [2024] Materialia · DOI: 10.1016/j.mtla.2024.102221
"Atom probe tomography of segregation at grain boundaries and gas bubbles in neutron irradiated U-10 wt% Mo fuel" Andrew Hoffman, Mukesh Bachhav, Assel Aitkaliyeva, Yaqiao Wu, Brandon Miller, Dennis Keiser, Jian Gan, Haiming Wen, Maalavan Arivu, [2024] Materials Letters · DOI: 10.1016/j.matlet.2024.136414
"Summary Report on Ion Irradiation Study of Ceramic Coating on Suppressing FCCI" Haiyan Wang, Yizhi Zhang, Yifan Zhang, Jiawei Song, Yibin Miao, Peter Mouche, Kun Mo, Bei Ye, Abdellatif Yacout, Brandon Miller, Laura Hawkins, Jian Gan, [2024] · DOI: 10.2172/2462693
"Contributions to the mechanistic understanding of the microstructural evolution in irradiated U-Mo dispersion fuel" Charlyne A. Smith, Tsvetoslav R. Pavlov, William A. Hanson, Kaustubh K. Bawane, Mukesh N. Bachhav, Brandon D. Miller, Tammy L. Trowbridge, Jian Gan, Jeffrey J. Giglio, Alexander J. Winston, Jody L. Henley, Adam B. Robinson, Dennis D. Keiser, Irina Y. Glagolenko, B. Ye, Z.-G. Mei, Laura M. Jamison, Gerard L. Hofman, Abdellatif M. Yacout, Sven Van den Berghe, Ann Leenaers, Daniele Salvato, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154789
"Evidence of Xe-incorporation in the bubble superlattice in irradiated U-Mo fuel" Mukesh Bachhav, Boopathy Kombaiah, Charlyne Smith, Assel Aitkaliyeva, Lingfeng He, Dennis Keiser, James Madden, Adam Robinson, Jian Gan, Brandon Miller, [2023] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154743
"Status Report on Ion Irradiation Study of Ceramic Coating in Suppressing Fuel/Cladding Chemical Interaction" Brandon Miller, Laura Hawkins, Haiyan Wang, Jian Gan, [2023] · DOI: 10.2172/2462696
"The role of UC inclusions in the development of fission gas bubble superlattice neutron-irradiated monolithic U-10Mo fuels" Kaustubh Bawane, Jian Gan, Dennis Keiser, Daniele Salvato, Mukesh Bachhav, Jan-Fong Jue, Charlyne Smith, [2023] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154474
"Early self-organization of fission gas bubble superlattice formation in neutron-irradiated monolithic U-10Mo fuels" Kaustubh Bawane, Daniele Salvato, Mukesh Bachhav, Dennis Keiser, Brandon Miller, Jian Gan, Jan-Fong Jue, Dong Choe, Paul Gilbreath, William Hanson, Charlyne Smith, [2023] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154358
"A phase-field model for void and gas bubble superlattice formation in irradiated solids" Andrea Jokisaari, Daniel Schwen, Chao Jiang, Anton Schneider, Yongfeng Zhang, Cheng Sun, Jian Gan, Larry K. Aagesen, [2022] Computational Materials Science · DOI: 10.1016/j.commatsci.2022.111772
"Unveiling the interaction of nanopatterned void superlattices with irradiation cascades" Chao Jiang, Yifeng Che, Wei-Ying Chen, Yongfeng Zhang, Andrea M. Jokisaari, Larry K. Aagesen, Lin Shao, Jian Gan, Cheng Sun, [2022] Acta Materialia · DOI: 10.1016/j.actamat.2022.118282
"The effects of temperature and dose rate on the properties of irradiation induced void superlattices" Yongfeng Zhang, Chao Jiang, Jian Gan, Anton Schneider, [2022] Materialia · DOI: 10.1016/j.mtla.2022.101373
"The effect of elastic anisotropy on the symmetry selection of irradiation-induced void superlattices in cubic metals" Andrea M. Jokisaari, Larry Aagesen, Yongfeng Zhang, Miaomiao Jin, Chao Jiang, Sudipta Biswas, Cheng Sun, Jian Gan, Yipeng Gao, [2022] Computational Materials Science · DOI: 10.1016/j.commatsci.2022.111252 · ISSN: 0927-0256
"Dissociated prismatic loop punching by bubble growth in FCC metals" Yipeng Gao, Yongfeng Zhang, Chao Jiang, Jian Gan, Miaomiao Jin, [2021] Scientific Reports · DOI: 10.1038/s41598-021-92219-7 · ISSN: 2045-2322
Abstract

Materials performance can be significantly degraded due to bubble generation. In this work, the bubble growth process is elaborated in Cu by atomistic modeling to bridge the gap of experimental observations. Upon continuous He implantation, bubble growth is accommodated first by nucleation of dislocation network from bubble surface, then formation of dissociated prismatic dislocation loop (DPDL), and final DPDL emission in $$\langle 110\rangle$$ 110 directions. As the DPDL is found capable of collecting He atoms, this process is likely to assist the formation of self-organized bubble superlattice, which has been reported from experiments. Moreover, the pressurized bubble in solid state manifests the shape of an imperfect octahedron, built by Cu $$\{111\}$$ { 111 } surfaces, consistent with experiments. These atomistic details integrating experimental work fill the gap of mechanistic understanding of athermal bubble growth in Cu. Importantly, by associating with nanoindentation testings, DPDL punching by bubble growth arguably applies to various FCC (face-centered cubic) metals such as Au, Ag, Ni, and Al.

"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: 2731-5894
Abstract

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.

Graphical abstract

"Unraveling the Early-Stage Ordering of Krypton Solid Bubbles in Molybdenum: A Multimodal Study" Anton Schneider, Cheng Sun, Yongfeng Zhang, Shirish Chodankar, Dmytro Nykypanchuk, Jian Gan, Lynne Ecker, Simerjeet K. Gill, Ericmoore Jossou, [2021] The Journal of Physical Chemistry C · DOI: 10.1021/acs.jpcc.1c05591 · ISSN: 1932-7447
"TEM characterization of dislocation loops in proton irradiated single crystal ThO2" Xiang Liu, Tiankai Yao, Marat Khafizov, Aaron French, J. Matthew Mann, Lin Shao, Jian Gan, David H. Hurley, Lingfeng He, Kaustubh Bawane, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.152998
"Microstructural Changes and Chemical Analysis of Fission Products in Irradiated Uranium-7 wt.% Molybdenum Metallic Fuel Using Atom Probe Tomography" Brandon Miller, Jian Gan, Dennis Keiser, Ann Leenaers, S. Van den Berghe, Mitchell K. Meyer, Mukesh Bachhav, [2021] Applied Sciences · DOI: 10.3390/app11156905 · ISSN: 2076-3417

Understanding the microstructural and phase changes occurring during irradiation and their impact on metallic fuel behavior is integral to research and development of nuclear fuel programs. This paper reports systematic analysis of as-fabricated and irradiated low-enriched U-Mo (uranium-molybdenum metal alloy) fuel using atom probe tomography (APT). This study is carried out on U-7 wt.% Mo fuel particles coated with a ZrN layer contained within an Al matrix during irradiation. The dispersion fuel plates from which the fuel samples were extracted are irradiated at Belgian Nuclear Research Centre (SCK CEN) with burn-up of 52% and 66% in the framework of the SELENIUM (Surface Engineering of Low ENrIched Uranium-Molybdenum) project. The APT studies on U-Mo particles from as-fabricated fuel plates enriched to 19.8% revealed predominantly γ-phase U-Mo, along with a network of the cell boundary decorated with α-U, γ’-U2Mo, and UC precipitates along the grain boundaries. The corresponding APT characterization of irradiated fuel samples showed formation of fission gas bubbles enriched with solid fission products. The intermediate burnup sample showed a uniform distribution of the typical bubble superlattice with a radius of 2 nm arranged in a regular lattice, while the high burnup sample showed a non-uniform distribution of bubbles in grain-refined regions. There was no evidence of remnant α-U, γ’-U2Mo, and UC phases in the irradiated U-7 wt.% Mo samples.

"Noble gas bubbles in bcc metals: Ab initio-based theory and kinetic Monte Carlo modeling" Yongfeng Zhang, Larry K. Aagesen, Andrea M. Jokisaari, Cheng Sun, Jian Gan, Chao Jiang, [2021] Acta Materialia · DOI: 10.1016/j.actamat.2021.116961 · ISSN: 1359-6454
"A NEA review on innovative structural materials solutions, including advanced manufacturing processes for nuclear applications based on technology readiness assessment" C. Cabet, S. Cornet, Y. Dai, J. Gan, M. Hernández Mayoral, R. Hernández, A. Jianu, L. Malerba, S.A. Maloy, J. Marrow, S. Ohtsuka, N. Okubo, M.A. Pouchon, A. Puype, E. Stergar, M. Serrano, D. Terentyev, Y.G. Wang, A. Weisenburger, F. Balbaud, [2021] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2021.101006 · ISSN: 2352-1791
"Defect dynamics in γ-U, Mo, and their alloys" Yipeng Gao, Chao Jiang, Jian Gan, Miaomiao Jin, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.152893 · ISSN: 0022-3115
"Understanding spinodal and binodal phase transformations in U-50Zr" Amrita Sen, Adrian Wagner, Fei Teng, Mukesh Bachhav, Anter EI-Azab, Daniel Murray, Jian Gan, David H. Hurley, Janelle P. Wharry, Michael T. Benson, Lingfeng He, Tiankai Yao, [2021] Materialia · DOI: 10.1016/j.mtla.2021.101092 · ISSN: 2589-1529
"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 · ISSN: 1359-6454
"Self-assembly of solid nanoclusters in molybdenum under gas ion implantation" Chao Jiang, Ericmoore Jossou, Mehmet Topsakal, Simerjeet K. Gill, Lynne E. Ecker, Jian Gan, Cheng Sun, [2021] Scripta Materialia · DOI: 10.1016/j.scriptamat.2020.113651 · ISSN: 1359-6462
"Defect cluster and nonequilibrium gas bubble associated growth in irradiated UMo fuels – A cluster dynamics and phase field model" Wahyu Setyawan, Benjamin W. Beeler, Jian Gan, Douglas E Burkes, Shenyang Hu, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152441 · ISSN: 0022-3115
"Symmetry breaking during defect self-organization under irradiation" Yipeng Gao, Cheng Sun, Daniel Schwen, Chao Jiang, Jian Gan, Yongfeng Zhang, [2020] Materials Theory · DOI: 10.1186/s41313-020-00021-1 · ISSN: 2509-8012
Abstract

One of the most intriguing phenomena under radiation is the self-organization of defects, such as the void superlattices, which have been observed in a list of bcc and fcc metals and alloys when the irradiation conditions fall into certain windows defined by temperature and dose rate. A superlattice features a lattice parameter and a crystal structure. Previously, it has been shown that the superlattice parameter is given by the wavelength of vacancy concentration waves that develop when the uniform concentration field becomes unstable. This instability is driven thermodynamically by vacancy concentration supersaturation and affected by the irradiation condition. However, a theory that predicts the superlattice symmetry, i.e., the selection of superlattice structure, has remained missing decades after the first report of superlattices. By analyzing the nonlinear recombination between vacancies and self-interstitial-atoms (SIAs) in the discrete lattice space, this work establishes the physical connection between symmetry breaking and anisotropic SIA diffusion, allowing for predictions of void ordering during defect self-organization. The results suggest that while the instability is driven thermodynamically by vacancy supersaturation, the symmetry development is kinetically rather than thermodynamically driven. The significance of SIA diffusion anisotropy in affecting superlattice formation under irradiation is also indicated. Various superlattice structures can be predicted based on different SIA diffusion modes, and the predictions are in good agreement with atomistic simulations and previous experimental observations.

"α-U and ω-UZr2 in neutron irradiated U-10Zr annular metallic fuel" Luca Capriotti, Jason M. Harp, Xiang Liu, Yachun Wang, Fei Teng, Daniel J. Murray, Alex J. Winston, Jian Gan, Michael T. Benson, Lingfeng He, Tiankai Yao, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152536 · ISSN: 0022-3115
"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
"Disordering of helium gas bubble superlattices in molybdenum under ion irradiation and thermal annealing" Yipeng Gao, David J. Sprouster, Yongfeng Zhang, Di Chen, Yongqiang Wang, Lynne E. Ecker, Jian Gan, Cheng Sun, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152315 · ISSN: 0022-3115
"Atom Probe Tomography for Burnup and Fission Product Analysis for Nuclear Fuels" Lingfeng He, Joshua Kane, Xiang Liu, Jian Gan, Francois Vurpiliot, Mukesh Bachhav, [2020] Microscopy and Microanalysis · DOI: 10.1017/s1431927620023776 · ISSN: 1431-9276
"Systematic analysis on the primary radiation damage in Th1−xUxO2 fluorite systems" Chao Jiang, Jian Gan, David H. Hurley, Miaomiao Jin, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152144 · ISSN: 0022-3115
"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 · ISSN: 2589-1529
"A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT)" Jian Gan, Dennis Keiser, Jeffrey Giglio, Daniel Jädernäs, Ann Leenaers, Sven Van den Berghe, Mukesh Bachhav, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.151853 · ISSN: 0022-3115
"Bifurcation and Pattern Symmetry Selection in Reaction-Diffusion Systems with Kinetic Anisotropy" Yongfeng Zhang, Daniel Schwen, Chao Jiang, Jian Gan, Yipeng Gao, [2019] Scientific Reports · DOI: 10.1038/s41598-019-44303-2 · ISSN: 2045-2322
Abstract

Ordering and self-organization are critical in determining the dynamics of reaction-diffusion systems. Here we show a unique pattern formation mechanism, dictated by the coupling of thermodynamic instability and kinetic anisotropy. Intrinsically different from the physical origin of Turing instability and patterning, the ordered patterns we obtained are caused by the interplay of the instability from uphill diffusion, the symmetry breaking from anisotropic diffusion, and the reactions. To understand the formation of the void/gas bubble superlattices in crystals under irradiation, we establish a general theoretical framework to predict the symmetry selection of superlattice structures associated with anisotropic diffusion. Through analytical study and phase field simulations, we found that the symmetry of a superlattice is determined by the coupling of diffusion anisotropy and the reaction rate, which indicates a new type of bifurcation phenomenon. Our discovery suggests a means for designing target experiments to tailor different microstructural patterns.

"Irradiation-Dependent Helium Gas Bubble Superlattice in Tungsten" C. Sun, Y. Zhang, S. N. Chodankar, J. Gan, L. E. Ecker, D. J. Sprouster, [2019] Scientific Reports · DOI: 10.1038/s41598-019-39053-0 · ISSN: 2045-2322
Abstract

The implantation of noble gas atoms into metals at high gas concentrations can lead to the self-organization of nanobubbles into superlattices with symmetry similar to the metal host matrix. Here, we examine the influence of implantation parameters on the formation and structure of helium gas bubble superlattices within a tungsten host matrix to uncover mechanistic insight into the formation process. The determination of the size and symmetry of the gas bubbles was performed using a combination of small angle x-ray scattering and transmission electron microscopy. The former was demonstrated to be particularly useful in determining size and structure of the gas bubble superlattice as a function of irradiation conditions. Prior to the formation of a superlattice, we observe a persistent substructure characterized by inter-bubble spacings similar to those observable when the gas bubble superlattice has formed with very large ordering parameters. As the implantation fluence increases, the inter-bubble ordering parameter decreases, indicating improved ordering, until a superlattice is formed. Multiple implantation-specific differences were observed, including a temperature-dependent superlattice parameter that increases with increasing temperature and a flux-dependent superlattice parameter that decreases with increasing flux. The trends quantified here are in excellent agreement with our recent theoretical predictions for gas bubble superlattice formation and highlight that superlattice formation is strongly dependent on the diffusion of vacancy and implanted He atoms.

"Formation window of gas bubble superlattice in molybdenum under ion implantation" David J. Sprouster, Yongfeng Zhang, Di Chen, Yongqiang Wang, Lynne E. Ecker, Jian Gan, Cheng Sun, [2019] Physical Review Materials · DOI: 10.1103/physrevmaterials.3.103607 · ISSN: 2475-9953
"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
"Theoretical prediction and atomic kinetic Monte Carlo simulations of void superlattice self-organization under irradiation" Yongfeng Zhang, Daniel Schwen, Chao Jiang, Cheng Sun, Jian Gan, Xian-Ming Bai, Yipeng Gao, [2018] Scientific Reports · DOI: 10.1038/s41598-018-24754-9 · ISSN: 2045-2322
Abstract

Nano-structured superlattices may have novel physical properties and irradiation is a powerful mean to drive their self-organization. However, the formation mechanism of superlattice under irradiation is still open for debate. Here we use atomic kinetic Monte Carlo simulations in conjunction with a theoretical analysis to understand and predict the self-organization of nano-void superlattices under irradiation, which have been observed in various types of materials for more than 40 years but yet to be well understood. The superlattice is found to be a result of spontaneous precipitation of voids from the matrix, a process similar to phase separation in regular solid solution, with the symmetry dictated by anisotropic materials properties such as one-dimensional interstitial atom diffusion. This discovery challenges the widely accepted empirical rule of the coherency between the superlattice and host matrix crystal lattice. The atomic scale perspective has enabled a new theoretical analysis to successfully predict the superlattice parameters, which are in good agreement with independent experiments. The theory developed in this work can provide guidelines for designing target experiments to tailor desired microstructure under irradiation. It may also be generalized for situations beyond irradiation, such as spontaneous phase separation with reaction.

"Microstructural characterization of as-fabricated and irradiated U-Mo fuel using SEM/EBSD" Jian Gan, Dennis Keiser, James Madden, Mukesh Bachhav, Jan-Fong Jue, Adam Robinson, Daniel Jadernas, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.06.007
"Formation and self-organization of void superlattices under irradiation: A phase field study" Yongfeng Zhang, Daniel Schwen, Chao Jiang, Cheng Sun, Jian Gan, Yipeng Gao, [2018] Materialia · DOI: 10.1016/j.mtla.2018.04.003 · ISSN: 2589-1529
"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
"Formation of tetragonal gas bubble superlattice in bulk molybdenum under helium ion implantation" D.J. Sprouster, K. Hattar, L.E. Ecker, L. He, Y. Gao, Y. Zhang, J. Gan, C. Sun, [2018] Scripta Materialia · DOI: 10.1016/j.scriptamat.2018.01.023 · ISSN: 1359-6462
"Laser and Pressure Resistance Weld of Thin-Wall Cladding for LWR Accident-Tolerant Fuels" N. Jerred, E. Perez, D. C. Haggard, J. Gan, [2018] JOM · DOI: 10.1007/s11837-017-2697-8
"Transmission electron microscopy investigation of neutron irradiated Si and ZrN coated UMo particles prepared using FIB" B.D. Miller, A. Leenaers, S. Van den Berghe, J. Gan, J.W. Madden, D.D. Keiser, W. Van Renterghem, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.10.016
"Ab initio theory of noble gas atoms in bcc transition metals" Yongfeng Zhang, Yipeng Gao, Jian Gan, Chao Jiang, [2018] Physical Chemistry Chemical Physics · DOI: 10.1039/c8cp01817k · ISSN: 1463-9076

Systematic ab initio calculations based on density functional theory have been performed to gain fundamental understanding of the interactions between noble gas atoms (He, Ne, Ar and Kr) and bcc transition metals in groups 5B (V, Nb and Ta), 6B (Cr, Mo and W) and 8B (Fe).

"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
"Overview of BES-GBS Project: The Role of Anisotropy on the Self-Organization of Gas Bubble Superlattice [PowerPoint]" Yongfeng Zhang, Jian Gan, [2017] · DOI: 10.2172/1468769
"TEM characterization of irradiated U-7Mo/Mg dispersion fuel" D.D. Keiser, B.D. Miller, J.F. Jue, A.B. Robinson, J. Madden, J. Gan, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.07.030
"Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density" B.D. Miller, D.D. Keiser, J.F. Jue, J.W. Madden, A.B. Robinson, H. Ozaltun, G. Moore, M.K. Meyer, J. Gan, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.05.035
"Microstructural characterization of an irradiated RERTR-6 U-7Mo/AA4043 alloy dispersion fuel plate specimen blister-tested to a final temperature of 500 °C" Jan-Fong Jue, Jian Gan, Brandon D. Miller, Adam B. Robinson, James W. Madden, M. Ross Finlay, Glenn Moore, Pavel Medvedev, Mitch Meyer, Dennis D. Keiser, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.02.038
"Status Report on Pressure Resistance Weld Development for FeCrAl Thin-Wall Cladding" Emmanuel Perez, Nathan Jerred, Jian Gan, [2017] · DOI: 10.2172/1483623
"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 · EID: 2-s2.0-85000956312
"Observed Changes in As-Fabricated U-10Mo Monolithic Fuel Microstructures After Irradiation in the Advanced Test Reactor" Jan-Fong Jue, Brandon Miller, Jian Gan, Adam Robinson, James Madden, Dennis Keiser, [2017] JOM · DOI: 10.1007/s11837-017-2564-7 · EID: 2-s2.0-85028761821
"High-energy synchrotron study of in-pile-irradiated U-Mo fuels" Kun Mo, Bei Ye, Laura Jamison, Zhi-Gang Mei, Jian Gan, Brandon Miller, James Madden, Jun-Sang Park, Jonathan Almer, Sumit Bhattacharya, Yeon Soo Kim, Gerard L. Hofman, Abdellatif M. Yacout, Yinbin Miao, [2016] Scripta Materialia · DOI: 10.1016/j.scriptamat.2015.12.019 · EID: 2-s2.0-84954199688
"Irradiation induced structural change in Mo2Zr intermetallic phase" D.D. Keiser, B.D. Miller, N. Eriksson, Y.H. Sohn, M. Kirk, J. Gan, [2016] Scripta Materialia · DOI: 10.1016/j.scriptamat.2016.04.041 · EID: 2-s2.0-84968883474
"Neutron irradiation effects in Fe and Fe-Cr at 300 °c" Yinbin Miao, Jian Gan, Maria A. Okuniewski, Stuart A. Maloy, James F. Stubbins, Wei-Ying Chen, [2016] Acta Materialia · DOI: 10.1016/j.actamat.2016.03.060 · EID: 2-s2.0-84979469688
"Systematic investigation of the misorientation- and temperature-dependent Kapitza resistance in CeO2" Xian-Ming Bai, Jian Gan, Aleksandr Chernatynskiy, [2016] International Journal of Heat and Mass Transfer · DOI: 10.1016/j.ijheatmasstransfer.2016.03.105 · EID: 2-s2.0-84964546988
"Influence of instrument conditions on the evaporation behavior of uranium dioxide with UV laser-assisted atom probe tomography" H.B. Henderson, J. Gan, M.V. Manuel, B. Valderrama, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.12.119 · ISSN: 0022-3115
"Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7 wt%Mo dispersion fuels" J. Gan, D.D. Keiser, A.B. Robinson, J.F. Jue, J.W. Madden, P.G. Medvedev, B.D. Miller, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.12.012 · ISSN: 0022-3115
"Atom probe study of irradiation-enhanced α precipitation in neutron-irradiated Fe-Cr model alloys" Yinbin Miao, Yaqiao Wu, Carolyn A. Tomchik, Kun Mo, Jian Gan, Maria A. Okuniewski, Stuart A. Maloy, James F. Stubbins, Wei-Ying Chen, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.04.005 · EID: 2-s2.0-84927944236
"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
"Characterization of swift heavy ion irradiation damage in ceria" Ram Devanathan, Janne Pakarinen, Jian Gan, Daniel Severin, Christina Trautmann, Todd R. Allen, Clarissa A. Yablinsky, [2015] Journal of Materials Research · DOI: 10.1557/jmr.2015.43 · EID: 2-s2.0-84929708754
"Comparison of preparation techniques for nuclear materials for transmission electron microscopy (TEM)" James W. Madden, Brandon D. Miller, James I. Cole, Jian Gan, Assel Aitkaliyeva, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.01.042 · EID: 2-s2.0-84922191788
"Erratum: Atom probe study of irradiation-enhanced α′ precipitation in neutron-irradiated Fe-Cr model alloys (J. Nucl. Mater. (2015) 462 (242-249))" Yinbin Miao, Yaqiao Wu, Carolyn A. Tomchik, Kun Mo, Jian Gan, Maria A. Okuniewski, Stuart A. Maloy, James F. Stubbins, Wei-Ying Chen, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.08.005 · EID: 2-s2.0-84947021978
"Investigation of material property influenced stoichiometric deviations as evidenced during UV laser-assisted atom probe tomography in fluorite oxides" Hunter B. Henderson, Clarissa A. Yablinsky, Jian Gan, Todd R. Allen, Michele V. Manuel, Billy Valderrama, [2015] Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms · DOI: 10.1016/j.nimb.2015.07.048 · EID: 2-s2.0-84938561925
"Thermal stability of fission gas bubble superlattice in irradiated U-10Mo fuel" D.D. Keiser, B.D. Miller, A.B. Robinson, D.M. Wachs, M.K. Meyer, J. Gan, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.04.023 · EID: 2-s2.0-84929085193
"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
"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
"Irradiation performance of U-Mo monolithic fuel" J. GAN, J.F. JUE, D.D. KEISER, E. PEREZ, A. ROBINSON, D.M. WACHS, N. WOOLSTENHULME, G.L. HOFMAN, Y.S. KIM, M.K. MEYER, [2014] Nuclear Engineering and Technology · DOI: 10.5516/net.07.2014.706 · EID: 2-s2.0-84899685698
"Kapitza resistance of the grain boundaries in Ceria" [2014] Transactions of the American Nuclear Society · EID: 2-s2.0-84904609271
"Microstructural characterization of irradiated U-7Mo/Al-5Si dispersion fuel to high fission density" B.D. Miller, D.D. Keiser, A.B. Robinson, J.W. Madden, P.G. Medvedev, D.M. Wachs, J. Gan, [2014] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.08.052 · EID: 2-s2.0-84908221240
"Microstructural characterization of the irradiated nuclear fuels" B.D. Miller, D.D. Keiser, J. Jue, A.B. Robinson, J.W. Madden, P.G. Medvedev, D.M. Wachs, J. Gan, [2014] Microscopy and Microanalysis · DOI: 10.1017/s1431927614010769 · EID: 2-s2.0-84927947439
"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 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
"Performance of U-Mo fuel at low temperatures" [2014] Transactions of the American Nuclear Society · EID: 2-s2.0-84904597497
"Scanning electron microscopy analysis of fuel/matrix interaction layers in highlyirradiated U-Mo dispersion fuel plates with al and Al-Si alloy matrices" JAN-FONG JUE, BRANDON D. MILLER, JIAN GAN, ADAM B. ROBINSON, PAVEL MEDVEDEV, JAMES MADDEN, DAN WACHS, MITCH MEYER, DENNIS D. KEISER, [2014] Nuclear Engineering and Technology · DOI: 10.5516/net.07.2014.704 · EID: 2-s2.0-84899696398
"Superior corrosion resistance properties of TiN-based coatings on Zircaloy tubes in supercritical water" Liang Jiao, Jie Jian, Wenrui Zhang, Zhijie Jiao, Jian Gan, Hongbin Zhang, Xinghang Zhang, Haiyan Wang, Fauzia Khatkhatay, [2014] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.04.010 · EID: 2-s2.0-84900461531
"TEM, APT and hardness studies of neutron-irradiated ferritic Fe-Cr single crystals" [2014] Transactions of the American Nuclear Society · EID: 2-s2.0-84904682460
"Characterization of oxide fuel surface chemistry with atom probe tomography" [2013] Transactions of the American Nuclear Society · EID: 2-s2.0-84902800366
"Diffusion barrier properties of nitride-based coatings on fuel cladding" Jie Jian, Liang Jiao, Qing Su, Jian Gan, James I. Cole, Haiyan Wang, Fauzia Khatkhatay, [2013] Journal of Alloys and Compounds · DOI: 10.1016/j.jallcom.2013.06.108 · EID: 2-s2.0-84884223822
"High-resolution fiber optic temperature sensors using nonlinear spectral curve fitting technique" J. Gan, Q. K. Yu, Q. H. Zhang, Z. H. Liu, J. M. Bao, Z. H. Su, [2013] Review of Scientific Instruments · DOI: 10.1063/1.4802684 · EID: 2-s2.0-84877255145

A generic new data processing method is developed to accurately calculate the absolute optical path difference of a low-finesse Fabry-Perot cavity from its broadband interference fringes. The method combines Fast Fourier Transformation with nonlinear curve fitting of the entire spectrum. Modular functions of LabVIEW are employed for fast implementation of the data processing algorithm. The advantages of this technique are demonstrated through high performance fiber optic temperature sensors consisting of an infrared superluminescent diode and an infrared spectrometer. A high resolution of 0.01 °C is achieved over a large dynamic range from room temperature to 800 °C, limited only by the silica fiber used for the sensor.

"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 · EID: 2-s2.0-84880894907
"Size-dependent radiation tolerance in ion irradiated TiN/AlN nanolayer films" L. Jiao, F. Khatkhatay, M.S. Martin, J. Lee, L. Shao, X. Zhang, J.G. Swadener, Y.Q. Wang, J. Gan, J.I. Cole, H. Wang, I. Kim, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2013.05.035 · EID: 2-s2.0-84879082898
"Transmission electron microscopy investigation of krypton bubbles in polycrystalline CeO2" [2013] Nuclear Technology · EID: 2-s2.0-84879071544
"Advantages and disadvantages of using a focused ion beam to prepare TEM samples from irradiated U-10Mo monolithic nuclear fuel" J. Gan, J. Madden, J.F. Jue, A. Robinson, D.D. Keiser, B.D. Miller, [2012] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2012.01.022 · EID: 2-s2.0-84857399196
"Effects of irradiation on the microstructure of U-7Mo dispersion fuel with Al-2Si matrix" Jan-Fong Jue, Adam B. Robinson, Pavel Medvedev, Jian Gan, Brandon D. Miller, Daniel M. Wachs, Glenn A. Moore, Curtis R. Clark, Mitchell K. Meyer, M. Ross Finlay, Dennis D. Keiser, [2012] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2012.01.013 · EID: 2-s2.0-84860445491
"Mg as a matrix for low-enriched U-Mo dispersion fuel plates" [2012] Transactions of the American Nuclear Society · EID: 2-s2.0-84876383457
"TEM Characterization of the Irradiated Nuclear Fuels" B.D. Miller, D.D. Keiser, A.B. Robinson, J.W. Madden, P.G. Medvedev, D.M. Wachs, J. Gan, [2012] Microscopy and Microanalysis · DOI: 10.1017/s1431927612004023 · EID: 2-s2.0-85007967943

Extended abstract of a paper presented at Microscopy and Microanalysis 2012 in Phoenix, Arizona, USA, July 29 – August 2, 2012.

"TEM characterization of U-7Mo/Al-2Si dispersion fuel irradiated to intermediate and high fission densities" D.D. Keiser, B.D. Miller, A.B. Robinson, J.F. Jue, P. Medvedev, D.M. Wachs, J. Gan, [2012] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2012.02.001 · EID: 2-s2.0-84857484996
"TiN-based coatings on fuel cladding tubes for advanced nuclear reactors" Fauzia Khatkhatay, Liang Jiao, Greg Swadener, James I. Cole, Jian Gan, Haiyan Wang, Ickchan Kim, [2012] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2012.05.001 · EID: 2-s2.0-84862649998
"Microstructure of RERTR DU-alloys irradiated with krypton ions up to 100 dpa" D.D. Keiser, B.D. Miller, D.M. Wachs, T.R. Allen, M. Kirk, J. Rest, J. Gan, [2011] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2011.01.121 · EID: 2-s2.0-79953199692
"Microstructure of the irradiated U 3Si 2/Al silicide dispersion fuel" D.D. Keiser, B.D. Miller, J.-F. Jue, A.B. Robinson, J.W. Madden, P.G. Medvedev, D.M. Wachs, J. Gan, [2011] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2011.07.030 · EID: 2-s2.0-80053341123
"Electron microscopy characterization of an as-fabricated research reactor fuel plate comprised of U-7Mo particles dispersed in an Al-2Si alloy matrix" J. Gan, J.F. Jue, B.D. Miller, C.R. Clark, Dennis D. Keiser, [2010] Materials Characterization · DOI: 10.1016/j.matchar.2010.07.010 · EID: 2-s2.0-77957981800
"Kr ion irradiation study of the depleted-uranium alloys" D.D. Keiser, B.D. Miller, M.A. Kirk, J. Rest, T.R. Allen, D.M. Wachs, J. Gan, [2010] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2010.07.008 · EID: 2-s2.0-78349311578
"Microstructure study of U-7wt%Mo/Al-2wt%Si dispersion fuel focusing on bubble evolution" [2010] Transactions of the American Nuclear Society · EID: 2-s2.0-79551675781
"Transmission electron microscopy characterization of irradiated U-7Mo/Al-2Si dispersion fuel" D.D. Keiser, D.M. Wachs, A.B. Robinson, B.D. Miller, T.R. Allen, J. Gan, [2010] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2009.11.015 · EID: 2-s2.0-73449137504
"Proton irradiation study of GFR candidate ceramics" Yong Yang, Clayton Dickson, Todd Allen, Jian Gan, [2009] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2009.02.021 · EID: 2-s2.0-64649090820
"Assessment of failure mechanisms for GFR vented fuel pins using hexoloy cladding" [2008] International Conference on the Physics of Reactors 2008, PHYSOR 08 · EID: 2-s2.0-79953888826
"High temperature interface reactions of TiC, TiN, and SiC with palladium and rhodium" K WRIGHT, J GAN, D PETTI, P DEMKOWICZ, [2008] Solid State Ionics · DOI: 10.1016/j.ssi.2008.07.021 · EID: 2-s2.0-56949084028
"Radiation effects on the microstructure of a 9Cr-ODS alloy" T. R. Allen, R. C. Birtcher, S. Shutthanandan, S. Thevuthasan, J. Gan, [2008] JOM · DOI: 10.1007/s11837-008-0003-5 · EID: 2-s2.0-46949091103
"Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation" J. Gan, J.I. Cole, M.K. Miller, J.T. Busby, S. Shutthanandan, S. Thevuthasan, T.R. Allen, [2008] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2007.11.001 · EID: 2-s2.0-40049111514
"Small-scale specimen testing of monolithic fuels and structural materials" [2008] Transactions of the American Nuclear Society · EID: 2-s2.0-55249117240
"Fuel development for gas-cooled fast reactors" R. Fielding, J. Gan, M.K. Meyer, [2007] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2007.05.013 · EID: 2-s2.0-34547837507
"Gas-cooled fast reactor fuel fabrication" Mitch Meyer, Jan-Fong Jue, Jian Gan, Randall Fielding, [2007] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2007.05.011 · EID: 2-s2.0-34547828125
"Gas-fast reactor fuel fabrication" [2006] Transactions of the American Nuclear Society · EID: 2-s2.0-33746065749
"Irradiated microstructure of alloy 800H" J.I. Cole, T.R. Allen, S. Shutthanandan, S. Thevuthasan, J. Gan, [2006] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2006.02.009 · EID: 2-s2.0-33744537735
"Microstructural development in advanced ferritic-martensitic steel HCM12A" L. Tan, J. Gan, G. Gupta, G.S. Was, E.A. Kenik, S. Shutthanandan, S. Thevuthasan, T.R. Allen, [2006] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2006.02.014 · EID: 2-s2.0-33746781354
"Microstructure evolution in ZrC irradiated with Kr ions" [2006] ASTM Special Technical Publication · EID: 2-s2.0-70249111888
"Radiation resistance of advanced ferritic-martensitic steel HCM12A" [2006] ASTM Special Technical Publication · EID: 2-s2.0-40849089764
"Radiation response of a 9 Cr oxide dispersion strengthened ODS to heavy ion irradiation" [2006] Transactions of the American Nuclear Society · EID: 2-s2.0-33746096587
"Swelling and radiation-induced segregation in austentic alloys" J.I. Cole, J. Gan, G.S. Was, R. Dropek, E.A. Kenik, T.R. Allen, [2005] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2005.02.008 · EID: 2-s2.0-20444500175
"The stability of 9Cr-ODS oxide particles under heavy-ion irradiation" [2005] Nuclear Science and Engineering · EID: 2-s2.0-27744573453
"Radiation effects in ZrC" [2004] Transactions of the American Nuclear Society · EID: 2-s2.0-33244484160
"The effect of oversized solute additions on the microstructure of 316SS irradiated with 5 MeV Ni++ ions or 3.2 MeV protons" E.P Simonen, S.M Bruemmer, L Fournier, B.H Sencer, G.S Was, J Gan, [2004] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2003.11.002 · EID: 2-s2.0-0942266719
"Assessment of materials for accelerator applications using proton irradiation" [2003] International Meeting on Nuclear Applications of Accelerator Technology: Accelerator Application in a Nuclear Renaissance · EID: 2-s2.0-2642524609
"Development of radiation-tolerant austenitic stainless steels for advanced reactor applications" [2003] Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy · EID: 2-s2.0-2642545798
"Effect of Zr on the irradiated microstructure and hardening in 304 stainless steel" [2003] Fusion Science and Technology · EID: 2-s2.0-0038454570
"The irradiated microstructure of ferritic-martensitic steel T91 and 9Cr-ODS" [2003] Materials Research Society Symposium - Proceedings · EID: 2-s2.0-2442606552
"Emulation of neutron irradiation effects with protons: Validation of principle" J.T Busby, T Allen, E.A Kenik, A Jensson, S.M Bruemmer, J Gan, A.D Edwards, P.M Scott, P.L Andreson, G.S Was, [2002] Journal of Nuclear Materials · DOI: 10.1016/s0022-3115(01)00751-6 · EID: 2-s2.0-0036468307
"Microstructure characterization of dislocation wall structure in aluminum using transmission electron microscopy" J. S. Vetrano, M. A. Khaleel, J. Gan, [2002] Journal of Engineering Materials and Technology, Transactions of the ASME · DOI: 10.1115/1.1479178 · EID: 2-s2.0-10844271576

The configuration of dislocation wall structures and the interactions between dislocations and dislocation walls play a significant role in the understanding of deformation processes in metals. Samples of single-crystal aluminum deformed by tensile-straining (15%) were analyzed using TEM. In tensile-deformed (15%) single crystal aluminum, a cell structure is well developed and dislocations in the cell boundaries consist of either one set of Burgers vector or two sets of Burgers vector. The three-dimensional image of cell wall structure, misorientation angle across the cell boundaries and the Burgers vectors of dislocations in the cell boundaries are characterized.

"Erratum: Microstructure evolution in austenistic Fe-Cr-Ni alloys irradiated with protons: Comparison with neutron-irradiated microstructures (Journal of Nuclear Materials (2001) 297 (161-175) PII: S0022311501006158)" G.S. Was, J. Gan, [2001] Journal of Nuclear Materials · DOI: 10.1016/s0022-3115(01)00671-7 · EID: 2-s2.0-0035478602
"Microstructure evolution in austenitic Fe-Cr-Ni alloys irradiated with rotons: Comparison with neutron-irradiated microstructures" G.S Was, J Gan, [2001] Journal of Nuclear Materials · DOI: 10.1016/s0022-3115(01)00615-8 · EID: 2-s2.0-0035426642
"Microstructure evolution in charged particle irradiated 316 SS modified to reduce radiation damage" [2001] Materials Research Society Symposium - Proceedings · EID: 2-s2.0-17044453002
"Modeling of microstructure evolution in austenitic stainless steels irradiated under light water reactor condition" G.S. Was, R.E. Stoller, J. Gan, [2001] Journal of Nuclear Materials · DOI: 10.1016/s0022-3115(01)00673-0 · EID: 2-s2.0-0035476753
"Correlation between swelling and radiation-induced segregation in iron-chromium-nickel alloys" [2000] ASTM Special Technical Publication · EID: 2-s2.0-0034476579
"Microchemistry and microstructure evolution in proton-irradiated austenitic stainless steels" [1999] Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors - · EID: 2-s2.0-0033489184
"Microchemistry and microstructure of proton-irradiated austenitic alloys: toward an understanding of irradiation effects in LWR core components" T.R Allen, J.T Busby, J Gan, D Damcott, D Carter, M Atzmon, E.A Kenik, G.S Was, [1999] Journal of Nuclear Materials · DOI: 10.1016/s0022-3115(98)00897-6 · EID: 2-s2.0-0032653806
"Microchemistry of proton-irradiated austenitic alloys under conditions relevant to LWR core components" [1999] Materials Research Society Symposium - Proceedings · EID: 2-s2.0-0032591964
"Modeling of microstructure evolution in austenitic stainless steels irradiated under light water reactor conditions" [1999] Materials Research Society Symposium - Proceedings · EID: 2-s2.0-0032591963
"Dependence of proton irradiated microstructure on dose, temperature and composition of austenitic stainless steels" [1997] Materials Research Society Symposium - Proceedings · EID: 2-s2.0-0030677285
Source: ORCID/CrossRef using DOI
NSUF Research Collaborations

In-situ irradiation of ZrC and ZrN above 800 C - FY 2024 RTE 1st Call, #24-4892

In Situ TEM Investigation on Fission Gas Behavior in U-10Zr - FY 2018 RTE 1st Call, #18-1226

Microstructural characterization of 21% burn-up MOX fuel - FY 2017 RTE 3rd Call, #17-1043

Post-irradiation observation following high-rate self-ion irradiation of previously neutron-irradiated 304 stainless steel - FY 2017 RTE 3rd Call, #17-1055

Investigation of gas bubble behavior under ion irradiation - FY 2017 RTE 2nd Call, #17-912

Post Irradiation Examination of Fiber Optic Temperature Sensors for In-Pile Temperature Monitor and Control for Advanced Test Reactor - FY 2017 RTE 2nd Call, #17-953

The window of gas-bubble superlattice formation in bcc metals - FY 2017 RTE 1st Call, #16-846

Characterization of ferritic steels Fe-9Cr and 9Cr2WYT ODS alloys irradiated in ATR - FY 2017 RTE 1st Call, #16-813

In Situ Observation of Lunar Crater Features in Xe Irradiated UO2 at High Dose - FY 2016 RTE 2nd Call, #16-657

Lattice structure evolution in ion irradiated UO2. - FY 2014 RTE 3rd Call, #14-513

Transmission Electron Microscopy Study of the Microstructure Evolution in Kr Irradiated UO2 - FY 2014 RTE 2nd Call, #12-483

Microstructure Evolution in Ion Irradiated UO2. - FY 2014 RTE 1st Call, #14-472

Study of the Microstructure of Kr and Xe Irradiated UO2 by Advanced Microscopy Techniques - FY 2013 RTE Solicitation, #13-431

Electron Backscatter Diffraction and Atom Probe Tomography to Study Krypton Segregation Behavior in Uranium Dioxide - FY 2013 RTE Solicitation, #13-409

Microstructures of Low-Dose He2+ and H+ Ion Irradiated UO2 - FY 2013 RTE Solicitation, #13-427

Electron Backscatter Diffraction and Atom Probe Tomography to Study Grain Boundary Chemistry Variation in Off Stoichiometric Uranium Dioxide Thin Films - FY 2013 RTE Solicitation, #13-429

Atom Probe Tomography to Study Helium Segregation and Bubble Formation in Uranium Dioxide - FY 2013 RTE Solicitation, #13-395

Atom Probe Tomography to Study Annealing Temperature Dependence on Krypton Bubble Clustering in Uranium Dioxide - FY 2013 RTE Solicitation, #13-397

Study of the Microstructure of Irradiated CeO2 by Advanced Microscopy Techniques - FY 2011 RTE Solicitation, #11-327

Corrosion Test in Supercritical Water for Nitride-based Coatings on LWR Cladding - FY 2011 RTE Solicitation, #11-284