Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding B Maier, H Yeom, G Johnson, T Dabney, J Walters, P Xu, J Romero, ... Journal of Nuclear Materials 519, 247-254, 2019 | 124 | 2019 |
Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors B Maier, H Yeom, G Johnson, T Dabney, J Walters, J Romero, H Shah, ... Jom 70, 198-202, 2018 | 89 | 2018 |
Evaluation of steam corrosion and water quenching behavior of zirconium-silicide coated LWR fuel claddings H Yeom, C Lockhart, R Mariani, P Xu, M Corradini, K Sridharan Journal of Nuclear Materials 499, 256-267, 2018 | 74 | 2018 |
Synthesis and sintering of UN-UO2 fuel composites BJ Jaques, J Watkins, JR Croteau, GA Alanko, B Tyburska-Püschel, ... Journal of Nuclear Materials 466, 745-754, 2015 | 72 | 2015 |
Characterization of structural defects in nuclear graphite IG-110 and NBG-18 G Zheng, P Xu, K Sridharan, T Allen Journal of Nuclear Materials 446 (1-3), 193-199, 2014 | 71 | 2014 |
Magnetron sputter deposition of zirconium-silicide coating for mitigating high temperature oxidation of zirconium-alloy H Yeom, B Maier, R Mariani, D Bai, S Fronek, P Xu, K Sridharan Surface and Coatings Technology 316, 30-38, 2017 | 51 | 2017 |
Quantifying the three-dimensional damage and stress redistribution mechanisms of braided SiC/SiC composites by in situ volumetric digital image correlation BP Croom, P Xu, EJ Lahoda, CP Deck, X Li Scripta Materialia 130, 238-241, 2017 | 51 | 2017 |
Oxidation behavior of grain boundary engineered alloy 690 in supercritical water environment P Xu, LY Zhao, K Sridharan, TR Allen Journal of Nuclear Materials 422 (1-3), 143-151, 2012 | 48 | 2012 |
Influence of sulfate salt type on passive film of steel in simulated concrete pore solution P Xu, L Jiang, MZ Guo, J Zha, L Chen, C Chen, N Xu Construction and Building Materials 223, 352-359, 2019 | 44 | 2019 |
Inhibition effect and mechanism of polyacrylamide for steel corrosion in simulated concrete pore solution F Zhi, L Jiang, M Jin, P Xu, B Xiao, Q Jiang, L Chen, Y Gu Construction and Building Materials 259, 120425, 2020 | 41 | 2020 |
Uranium nitride-silicide advanced nuclear fuel: higher efficiency and greater safety TL Wilson, EE Moore, D Adorno Lopes, V Kocevski, E Sooby Wood, ... Advances in Applied Ceramics 117 (1_suppl), 76-81, 2018 | 35 | 2018 |
Effect of sulfate ions on corrosion of reinforced steel treated by DNA corrosion inhibitor in simulated concrete pore solution C Chen, L Jiang, MZ Guo, P Xu, L Chen, J Zha Construction and Building Materials 228, 116752, 2019 | 34 | 2019 |
Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation L He, M Khafizov, C Jiang, B Tyburska-Püschel, BJ Jaques, P Xiu, P Xu, ... Acta Materialia 208, 116778, 2021 | 33 | 2021 |
Development of surface coatings for enhanced accident tolerant fuel H Shah, J Romero, P Xu, B Maier, G Johnson, J Walters, T Dabney, ... Water React. Fuel Perform. Meet., Jeju Island, Korea, 2017 | 32 | 2017 |
Processing of magnesia–pyrochlore composites for inert matrix materials SJ Yates, P Xu, J Wang, JS Tulenko, JC Nino Journal of nuclear materials 362 (2-3), 336-342, 2007 | 27 | 2007 |
Nanocrystalline diamond protects Zr cladding surface against oxygen and hydrogen uptake: Nuclear fuel durability enhancement J Škarohlíd, P Ashcheulov, R Škoda, A Taylor, R Čtvrtlík, J Tomáštík, ... Scientific reports 7 (1), 6469, 2017 | 25 | 2017 |
Scalable preparation of high-dispersion g-C3N4 via GQDs-assisted ultrasonic exfoliation for accelerating cement hydration WJ Long, P Xu, Y Yu, F Xing, C He Cement and Concrete Composites 134, 104782, 2022 | 23 | 2022 |
Unveiling hermetic failure of ceramic tubes by digital image correlation and acoustic emission CH Bumgardner, FM Heim, DC Roache, A Jarama, P Xu, R Lu, ... Journal of the American Ceramic Society 103 (3), 2146-2159, 2020 | 23 | 2020 |
Zr alloy protection against high-temperature oxidation: Coating by a double-layered structure with active and passive functional properties I Kratochvílová, P Ashcheulov, J Škarohlíd, R Škoda, J Kopeček, P Sajdl, ... Corrosion Science 163, 108270, 2020 | 21 | 2020 |
SiC matrix fuel cladding tube with spark plasma sintered end plugs P Xu, EJ Lahoda, L Hallstadius, JH Choi, S Higuchi, F Kano US Patent 9,455,053, 2016 | 21 | 2016 |