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The last 5 uploaded publications
In situ high-temperature 3D imaging of the damage evolution in a SiC nuclear fuel cladding material
Guanjie Yuan, J. Paul Forna-Kreutzer, Peng Xu, S. Gonderman, Christian P. Deck, Luke Olson, Edward J. Lahoda, Robert O. Ritchie, Dong Liu (2023). In situ high-temperature 3D imaging of the damage evolution in a SiC nuclear fuel cladding material. Materials & Design, 227, pp. 111784-111784, DOI: 10.1016/j.matdes.2023.111784.
Article273 days agoIn situ X-ray computed micro-tomography imaging of failure processes in Cr-coated Zircaloy nuclear fuel cladding materials
Guanjie Yuan, J. Paul Forna-Kreutzer, Jon Ell, Harold Barnard, Benjamin Maier, Edward J. Lahoda, Jorie Walters, Robert O. Ritchie, Dong Liu (2023). In situ X-ray computed micro-tomography imaging of failure processes in Cr-coated Zircaloy nuclear fuel cladding materials. Materials & Design, 234, pp. 112373-112373, DOI: 10.1016/j.matdes.2023.112373.
Article273 days agoInvestigation of the temperature-dependent failure processes in PVD Cr-coated ZIRLO nuclear fuel cladding using in situ X-ray micro-tomography imaging
Guanjie Yuan, Martin Ševeček, David H. Cook, Dula Parkinson, Robert O. Ritchie, Dong Liu (2025). Investigation of the temperature-dependent failure processes in PVD Cr-coated ZIRLO nuclear fuel cladding using in situ X-ray micro-tomography imaging. , 512, DOI: https://doi.org/10.1016/j.surfcoat.2025.132376.
Article31 days agoImproved damage tolerance of SiC-based nuclear fuel cladding with novel multi-layered SiC coating design at 1200 °C
Guanjie Yuan, David H. Cook, Harold Barnard, Edward J. Lahoda, Peng Xu, Robert O. Ritchie, Dong Liu (2025). Improved damage tolerance of SiC-based nuclear fuel cladding with novel multi-layered SiC coating design at 1200 °C. , 256, DOI: https://doi.org/10.1016/j.matdes.2025.114260.
Article31 days agoImproved damage tolerance of SiC-based nuclear fuel cladding with novel multi-layered SiC coating design at 1200 °C
Guanjie Yuan, David H. Cook, Harold Barnard, Edward J. Lahoda, Peng Xu, Robert O. Ritchie, Dong Liu (2025). Improved damage tolerance of SiC-based nuclear fuel cladding with novel multi-layered SiC coating design at 1200 °C. , 256, DOI: https://doi.org/10.1016/j.matdes.2025.114260.
Article31 days ago