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Di Yun
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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
1492022
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
1422002
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
612021
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
592021
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
592014
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
552020
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
512022
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
502022
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
482021
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
472016
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
412013
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
352011
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
332023
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
332021
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
322023
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
312017
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
292021
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
252021
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
232016
Development of Advanced Ultra-High Burnup SFR Metallic Fuel Concept- Project Overview
AE Wright, SL Hayes, TH Bauer, HJ Chichester, GL Hofman, JR Kennedy, ...
Transactions of the American Nuclear Society 106, 1102-1105, 2012
222012
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