| α-U and ω-UZr2 in neutron irradiated U-10Zr annular metallic fuel T Yao, L Capriotti, JM Harp, X Liu, Y Wang, F Teng, DJ Murray, ... Journal of Nuclear Materials 542, 152536, 2020 | 34 | 2020 |
| Fuel-cladding chemical interaction of a prototype annular U-10Zr fuel with Fe-12Cr ferritic/martensitic HT-9 cladding X Liu, L Capriotti, T Yao, JM Harp, MT Benson, Y Wang, F Teng, L He Journal of Nuclear Materials 544, 152588, 2021 | 22 | 2021 |
| Understanding spinodal and binodal phase transformations in U-50Zr T Yao, A Sen, A Wagner, F Teng, M Bachhav, EIA Anter, D Murray, J Gan, ... Materialia 16, 101092, 2021 | 17 | 2021 |
| Deformation twinning versus slip in Ni-based alloys, containing Pt2Mo-structured, Ni2Cr-typed precipitates HT Vo, K Dang, F Teng, M Schneider, BP Eftink, SA Maloy, JD Tucker, ... Materials & Design 207, 109820, 2021 | 15 | 2021 |
| Effect of stoichiometry on the evolution of thermally annealed long-range ordering in Ni–Cr alloys F Teng, DJ Sprouster, GA Young, JH Ke, JD Tucker Materialia 8, 100453, 2019 | 14 | 2019 |
| Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing F Cappia, K Wright, D Frazer, K Bawane, B Kombaiah, W Williams, ... Journal of Nuclear Materials 569, 153881, 2022 | 11 | 2022 |
| Investigation of the microstructure evolution of alpha uranium after in pile transient FG Di Lemma, X Liu, TV Holschuh II, CP Folsom, DJ Murray, F Teng, ... Journal of Nuclear Materials 542, 152467, 2020 | 11 | 2020 |
| Structure of the pellet-cladding interaction layer of a high-burnup Zr-Nb-O nuclear fuel cladding X Liu, MN Cinbiz, B Kombaiah, L He, F Teng, E Lacroix Journal of Nuclear Materials 556, 153196, 2021 | 9 | 2021 |
| Role of stoichiometry on ordering in Ni-Cr alloys F Teng, JD Tucker MRS Online Proceedings Library (OPL) 1809, 7-12, 2015 | 6 | 2015 |
| Irradiation Effects on Stability of δ-UZr2 phase in U-50 wt% Zr Alloy A Sen, M Bachhav, X Pu, F Teng, T Yao, JP Wharry Journal of Nuclear Materials 576, 154251, 2023 | 5 | 2023 |
| Small-scale mechanical testing and characterization of fuel cladding chemical interaction between HT9 cladding and advanced U-based metallic fuel alloy Y Wang, DM Frazer, F Cappia, F Teng, DJ Murray, T Yao, CD Judge, ... Journal of Nuclear Materials 566, 153754, 2022 | 5 | 2022 |
| Nanoscale redistribution of alloying elements in high-burnup AXIOM-2 (X2®) and their effects on in-reactor corrosion Z Yu, M Bachhav, F Teng, L He, A Couet Corrosion Science 190, 109652, 2021 | 5 | 2021 |
| Irradiation damage and IASCC of printed 316L for use as fuel cladding MD McMurtrey, RC O'Brien, C Sun, CH Shiau, F Teng Idaho National Lab.(INL), Idaho Falls, ID (United States), 2019 | 5 | 2019 |
| Grain subdivision and structural modifications by high-energy heavy ions in UO2 with different initial grain size F Cappia, M Cullison, T Chen, B Kombaiah, K Bawane, F Teng, J Madden, ... Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2022 | 4 | 2022 |
| The role of stoichiometry on ordering phase transformations in Ni–Cr alloys for nuclear applications F Teng, LJ Yu, O Ciuca, E Marquis, G Burke, JD Tucker Proceedings of the 18th International Conference on Environmental …, 2019 | 4 | 2019 |
| The advanced characterization, post-irradiation examination, and materials informatics for the development of ultra high-burnup annular U-10Zr metallic fuel T Yao, M Bachhav, FG Di Lemma, F Xu, F Teng, DJ Murray, MT Benson, ... Frontiers in Nuclear Engineering 1, 1050262, 2023 | 3 | 2023 |
| Microstructural and phase changes in alpha uranium investigated via in-situ studies and molecular dynamics FG Di Lemma, T Yao, D Salvato, L Capriotti, F Teng, AM Jokisaari, ... Journal of Nuclear Materials 577, 154341, 2023 | 3 | 2023 |
| Transmission electron microscopy based characterization of a U-20Pu-10Zr fuel irradiated in experimental breeder reactor-II T Yao, X Liu, Y Wang, F Teng, DJ Murray, M Meyer, MT Benson, ... Journal of Nuclear Materials 568, 153846, 2022 | 3 | 2022 |
| Nano-mechanical property assessment of a neutron-irradiated HT-9 steel cladding and a fuel-cladding chemical interaction region of a uranium–10 wt% zirconium nuclear fuel J Thomas, F Teng, D Murray, MA Okuniewski MRS Advances, 1-6, 2021 | 3 | 2021 |
| Effect of isothermal aging on Ni-Cr-based commercial alloys N Aerne, F Teng, JD Tucker 19th International Conference on Environmental Degradation of Materials in …, 2019 | 3 | 2019 |
