| Review on chromium coated zirconium alloy accident tolerant fuel cladding J Yang, M Steinbrück, C Tang, M Große, J Liu, J Zhang, D Yun, S Wang Journal of Alloys and Compounds 895, 162450, 2022 | 230 | 2022 |
| Precise Monte Carlo simulation of gamma-ray response functions for an NaI (Tl) detector HX Shi, BX Chen, TZ Li, D Yun Applied radiation and isotopes 57 (4), 517-524, 2002 | 151 | 2002 |
| Transient experiments on oxidation and degradation of Cr-coated Zircaloy in steam up to 1600℃ J Liu, C Tang, M Steinbrück, J Yang, U Stegmaier, M Große, D Yun, ... Corrosion Science 192, 109805, 2021 | 85 | 2021 |
| Oxidation behavior, thermal stability, and the coating/substrate interface evolution of CrN-coated Zircaloy under high-temperature steam J Liu, Z Hao, Z Cui, D Ma, J Lu, Y Cui, C Li, W Liu, S Xie, P Hu, P Huang, ... Corrosion Science 185, 109416, 2021 | 85 | 2021 |
| Distinct point defect behaviours in body-centered cubic medium-entropy alloy NbZrTi induced by severe lattice distortion T Shi, Z Su, J Li, C Liu, J Yang, X He, D Yun, Q Peng, C Lu Acta Materialia 229, 117806, 2022 | 79 | 2022 |
| Systematic investigations on the coating degradation mechanism during the steam oxidation of Cr-coated Zry-4 at 1200° C J Liu, M Steinbrück, M Große, U Stegmaier, C Tang, D Yun, J Yang, Y Cui, ... Corrosion Science 202, 110310, 2022 | 76 | 2022 |
| Current state and prospect on the development of advanced nuclear fuel system materials: A review D Yun, C Lu, Z Zhou, Y Wu, W Liu, S Guo, T Shi, JF Stubbins Materials Reports: Energy 1 (1), 100007, 2021 | 75 | 2021 |
| Investigation of oxidation behaviors of coated Zircaloy as accident-tolerant fuel with CrAlN and CrAlSiN coatings in high-temperature steam J Liu, Z Cui, D Ma, J Lu, Y Cui, C Li, W Liu, Z Hao, P Hu, M Yao, P Huang, ... Corrosion Science 175, 108896, 2020 | 68 | 2020 |
| Synchrotron study on load partitioning between ferrite/martensite and nanoparticles of a 9Cr ODS steel K Mo, Z Zhou, Y Miao, D Yun, HM Tung, G Zhang, W Chen, J Almer, ... Journal of Nuclear Materials 455 (1-3), 376-381, 2014 | 63 | 2014 |
| Enhancing the radiation tolerance of high-entropy alloys via solute-promoted chemical heterogeneities Z Su, J Ding, M Song, L Jiang, T Shi, Z Li, S Wang, F Gao, D Yun, E Ma, ... Acta Materialia 245, 118662, 2023 | 61 | 2023 |
| 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 | 61 | 2021 |
| Irradiation induced microstructure evolution in nanostructured materials: a review W Liu, Y Ji, P Tan, H Zang, C He, D Yun, C Zhang, Z Yang Materials 9 (2), 105, 2016 | 55 | 2016 |
| Restraining the Cr-Zr interdiffusion of Cr-coated Zr alloys in high temperature environment: A Cr/CrN/Cr coating approach J Yang, L Shang, J Sun, S Bai, S Wang, J Liu, D Yun, D Ma Corrosion Science 214, 111015, 2023 | 54 | 2023 |
| Steam oxidation of Cr-coated Sn-containing Zircaloy solid rod at 1000° C J Liu, Z Cui, Z Hao, D Ma, J Lu, Y Cui, C Li, W Liu, S Xie, P Hu, P Huang, ... Corrosion Science 190, 109682, 2021 | 45 | 2021 |
| Irradiation effects in UO2 and CeO2 B Ye, A Oaks, M Kirk, D Yun, WY Chen, B Holtzman, JF Stubbins Journal of nuclear materials 441 (1-3), 525-529, 2013 | 43 | 2013 |
| Kinetic Monte Carlo model of defect transport and irradiation effects in La-doped CeO2 A Oaks, D Yun, B Ye, WY Chen, JF Stubbins Journal of nuclear materials 414 (2), 145-149, 2011 | 36 | 2011 |
| Investigation of the oxidation mechanisms of superlattice Cr-CrN/TiSiN-Cr multilayer coatings on Zircaloy substrates under high-temperature steam atmospheres J Liu, Z Hao, Z Cui, D Ma, J Lu, Y Cui, C Li, W Liu, S Xie, P Huang, G Bai, ... Corrosion Science 192, 109782, 2021 | 35 | 2021 |
| Grain growth and pore coarsening in dense nano‐crystalline UO2+x fuel pellets T Yao, K Mo, D Yun, S Nanda, AM Yacout, J Lian Journal of the American Ceramic Society 100 (6), 2651-2658, 2017 | 35 | 2017 |
| In situ synchrotron tensile investigations on 14YWT, MA957, and 9-Cr ODS alloys JL Lin, K Mo, D Yun, Y Miao, X Liu, H Zhao, DT Hoelzer, JS Park, J Almer, ... Journal of Nuclear Materials 471, 289-298, 2016 | 26 | 2016 |
| An initial assessment of a mechanistic model, GRASS-SST, in U–Pu–Zr metallic alloy fuel fission-gas behavior simulations D Yun, J Rest, GL Hofman, AM Yacout Journal of Nuclear Materials 435 (1-3), 153-163, 2013 | 26 | 2013 |
Kun MoArgonne National Laboratoryanl.gov의 이메일 확인됨
