Self-accelerated corrosion of nuclear waste forms at material interfaces X Guo, S Gin, P Lei, T Yao, H Liu, DK Schreiber, D Ngo, G Viswanathan, ... Nature materials 19 (3), 310-316, 2020 | 84 | 2020 |
Current development of body-centered cubic high-entropy alloys for nuclear applications T Shi, PH Lei, X Yan, J Li, YD Zhou, YP Wang, ZX Su, YK Dou, XF He, ... Tungsten 3 (2), 197-217, 2021 | 48 | 2021 |
Spark plasma sintering (SPS) densified U3Si2 pellets: Microstructure control and enhanced mechanical and oxidation properties B Gong, T Yao, P Lei, J Harp, AT Nelson, J Lian Journal of Alloys and Compounds 825, 154022, 2020 | 44 | 2020 |
U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels B Gong, T Yao, P Lei, L Cai, KE Metzger, EJ Lahoda, FA Boylan, ... Journal of Nuclear Materials 534, 152147, 2020 | 34 | 2020 |
Cr-doped U3Si2 composite fuels under steam corrosion B Gong, L Cai, P Lei, KE Metzger, EJ Lahoda, FA Boylan, K Yang, J Fay, ... Corrosion Science 177, 109001, 2020 | 23 | 2020 |
Chemical durability and surface alteration of lanthanide zirconates (A2Zr2O7: A= La-Yb) K Yang, Y Wang, P Lei, T Yao, D Zhao, J Lian Journal of the European Ceramic Society 41 (12), 6018-6028, 2021 | 21 | 2021 |
A systematic study of lanthanide titanates (A2Ti2O7) chemical durability: corrosion mechanisms and control parameters K Yang, P Lei, T Yao, B Gong, Y Wang, M Li, J Wang, J Lian Corrosion Science 185, 109394, 2021 | 21 | 2021 |
Microstructural Evolution of Dy2O3-TiO2 Powder Mixtures during Ball Milling and Post-Milled Annealing J Huang, G Ran, J Lin, Q Shen, P Lei, X Wang, N Li Materials 10 (1), 19, 2016 | 20 | 2016 |
High temperature oxidation behavior and mechanism of Al0. 3CuCrFeNi2 high-entropy alloy with a coherent γ/γ'microstructure G Huang, J Wu, R Yuan, Y Li, F Meng, P Lei, C Lu, F Cao, Y Shen Corrosion Science 195, 109984, 2022 | 18 | 2022 |
Microstructure Analysis of Neutron Absorber Al/B4C Metal Matrix Composites J Lin, G Ran, P Lei, C Ye, S Huang, S Zhao, N Li Metals 7 (12), 567, 2017 | 15 | 2017 |
Investigation of mechanical properties and proton irradiation behaviors of SA-738 Gr. B steel used as reactor containment Y Ma, G Ran, N Chen, P Lei, Q Shen Nuclear Materials and Energy 8, 18-22, 2016 | 14 | 2016 |
Effect of crystal orientation on hardness of He+ ion irradiated tungsten S Huang, G Ran, P Lei, N Chen, S Wu, N Li, Q Shen Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2017 | 13 | 2017 |
Spark plasma sintering-densified vanadinite apatite-based chlorine waste forms with high thermal stability and chlorine confinement P Lei, T Yao, B Gong, W Zhu, G Ran, J Lian Journal of Nuclear Materials 528, 151857, 2020 | 12 | 2020 |
Highly stable nanocrystalline oxide dispersion strengthened alloys with outstanding helium bubble suppression X Yan, Z Su, J Liang, T Shi, B Sun, P Lei, D Yun, T Shen, G Ran, C Lu Journal of Nuclear Materials 557, 153283, 2021 | 8 | 2021 |
Reply to: How much does corrosion of nuclear waste matrices matter X Guo, S Gin, P Lei, T Yao, H Liu, DK Schreiber, D Ngo, G Viswanathan, ... Nature Materials 19 (9), 962-963, 2020 | 8 | 2020 |
Corrosion interactions between stainless steel and lead vanado-iodoapatite nuclear waste form part II T Yao, X Guo, P Lei, Y Wang, GS Frankel, J Lian npj Materials Degradation 4 (1), 15, 2020 | 8 | 2020 |
Microstructure analysis of Kr+ irradiation and post-irradiation corrosion of modified N36 zirconium alloy P Lei, G Ran, C Liu, Q Shen, R Zhang, C Ye, N Li, P Yang, Y Yang Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2017 | 7 | 2017 |
Enhanced crevice corrosion of stainless steel 316 by degradation of Cr-containing hollandite crevice former X Guo, P Lei, C Mohanty, T Yao, J Lian, GS Frankel Corrosion Science 205, 110462, 2022 | 6 | 2022 |
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 | 6 | 2022 |
In Situ TEM Study of Microstructure Evolution of Zr-Nb-Fe Alloy Irradiated by 800 keV Kr2+ Ions P Lei, G Ran, C Liu, C Ye, D Lv, J Lin, Y Wu, J Xu Materials 10 (4), 437, 2017 | 6 | 2017 |