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Tiankai Yao

Idaho National Laboratory

29H指数
199论文数
3.4K被引数
收录论文 76
发表时间
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Effects of processing technique on microstructural evolution of U–Zr alloy: A combined XRD and SEM analysis加工工艺对U-Zr合金微观结构演化的影响：XRD和SEM联合分析
errJournal of Nuclear Materials
IF3.2
err2026-09-23
err0
PREAI
errAnthony Albert Harrup; Mathias Boulanger; Sarah Cole; Mehmet Topsakal; Laura K. Sudderth; Karim Ahmed; Tiankai Yao; Ericmoore Jossou
err分享
err收藏
Influence of severe plastic deformation processing on grain refinement and neutron irradiation response in FeCrAl alloys严重塑性变形处理对FeCrAl合金晶粒细化和中子辐照响应的影响
errMaterials Science and Engineering A-Structural Materials Properties Microstructure and Processing
IF7
err2026-08-28
err0
PREAI
errJoshua Rittenhouse; Mukesh Bachhav; Laura Hawkins; Sohail Shah; Matthew Luebbe; Lingfeng He; Cameron Howard; David Frazer; Nedim Cinbiz; Tiankai Yao; Haiming Wen
err分享
err收藏
TEM characterization of two variants of fuel-cladding chemical interaction in a HT-9 Clad U-10Zr fuel. Variant 2: FCCI without a Zr rind透射电子显微镜对HT-9包壳U-10Zr燃料中两种燃料-包壳化学相互作用变体的表征。变体2：无Zr外壳的FCCI
errJournal of Nuclear Materials
IF3.2
err2026-08-12
err0
errOAAI
errBao-Phong Nguyen; Daniele Salvato; Sohail Shah; Fidelma Giulia Di Lemma; Luca Capriotti; Mukesh Bachhav; Tiankai Yao; Assel Aitkaliyeva; Yachun Wang
err分享
err收藏
Fuel Cladding Chemical Interaction and High Temperature Phase Transformation in U-10Zr Metallic FuelU-10Zr金属燃料的燃料包壳化学相互作用及高温相变
errMicroscopy and Microanalysis
IF3
err2026-07-27
err0
errOAAI
errEricmoore Jossou; Anthony Harrup; Sarah Cole; Tiankai Yao
err分享
err收藏
Fission products in fuel cladding chemical interaction (FCCI) region of ATR-irradiated HT9-clad U–10MTZ (10MTZ = 5Mo–4.3Ti–0.7Zr, wt%) metallic fuelATR辐照HT9包壳U–10MTZ（10MTZ=5Mo–4.3Ti–0.7Zr，wt%）金属燃料中裂变产物在燃料包壳化学相互作用（FCCI）区域
errMaterials Characterization
IF5.5
err2026-07-24
err0
errOAAI
errArnold Pradhan; Tiankai Yao; Sohail Shah; Jatuporn Burns; Mukesh Bachhav; Indrajit Charit; Colby B. Jensen; Yachun Wang
err分享
err收藏
Site specific porosity-thermal performance correlations in neutron irradiated U-10Zr fuel中子辐照U-10Zr燃料中位点的孔隙率-热性能相关性
errMaterials Today
IF22
err2026-05-05
err0
PREAI
errAnthony A. Harrup; Riley Moeykens; Michael Drakopoulos; Nghia T. Vo; Jana Howard; Colby B. Jensen; Tiankai Yao; Ericmoore Jossou
err分享
err收藏
Multi-scale, multi-modal characterization of silicon carbide cladding following safety testing in the Transient Reactor Test facility (TREAT)在瞬态反应堆试验设施（TREAT）安全测试后对碳化硅包壳的多尺度、多模态表征
errMaterials Characterization
IF5.5
err2026-05-04
err0
errOAAI
errGuang Yang; Tanner J. Mauseth; Arnold Pradhan; Sohail Shah; Cameron B. Howard; Tiankai Yao; Mario D. Matos; Jason L. Schulthess; Fei Teng; Daniel J. Murray; Mukesh N. Bachhav; Sean Gonderman; Jack Gazza; Madeline Anne Feltus; Fei Xu; Peng Xu
err分享
err收藏
Modern Measurement of Local Radial Thermal Conductivity of Irradiated He-Bonded U-10 wt. % Zr Annular Fuel: A cross-correlative study with electron probe microanalysis techniques
errJournal of Nuclear Materials
IF3.2
err2026-01-28
err0
PREAI
errCynthia Adkins; Matthew Goodson; Mary Meyer; Karen Wright; Ethan Hisle; Tiankai Yao; Luca Capriotti; Assel Aitkaliyeva; Tsvetoslav Pavlov
err分享
err收藏
High-resolution characterization of ceramic-metal interface of TiN coating on ferritic-steels for nuclear application核应用中TiN涂层在铁素体钢上的陶瓷-金属界面的高分辨率表征
errJournal of Nuclear Materials
IF3.2
err2025-12-23
err0
PREAI
errYuhan Li; Chao Jiang; Tiankai Yao; Haiyan Wang; Jian Gan
err分享
err收藏
Bridging multimodal microscopy for advanced characterization on nuclear fuel using machine learning利用机器学习实现多模态显微镜在核燃料先进表征中的桥梁作用
errFRONTIERS IN MECHANICAL ENGINEERING-SWITZERLAND
IF3
err2025-10-15
err0
errOAAI
errManda, Haarika; Zhao, Liang; Reddy Kancharla, Rahul; Xiao, Xianghui; Purushotham, Charith; Tang, Yalei; Xu, Peng; Yao, Tiankai; Xu, Fei
err分享
err收藏
Entrapment Behavior of Solid Surrogate Fission Products at Engineered UN Nano-Hetero-Interfaces Within Metallic Nuclear Fuels固体模拟裂变产物在金属核燃料中工程化UN纳米异质界面上的捕获行为
errAdvanced Materials Interfaces
IF4.4
err2025-10-02
err0
errOAAI
errJames Zillinger; Arnold Pradhan; Yizhou Lu; Randall Scott; Nathan Jerred; Mukesh Bachhav; Tiankai Yao; Samrat Choudhury; Indrajit Charit
err分享
err收藏
Nanoscale clustering and fission product segregation in irradiated annular U-10Zr fuel辐照环形U-10Zr燃料中的纳米尺度团簇和裂变产物偏聚
errJournal of Nuclear Materials
IF3.2
err2025-09-05
err0
PREAI
errArnold Pradhan; Sohail Shah; Daniele Salvato; Jason Harp; Luca Capriotti; Mukesh Bachhav; Indrajit Charit; Tiankai Yao
err分享
err收藏
High resolution microstructural, chemical studies and localized burnup analysis in an irradiated U10Zr metallic fuel高分辨率微观结构、化学研究以及在辐照U10Zr金属燃料中的局部燃耗分析
errMaterials Characterization
IF5.5
err2025-08-05
err0
PREAI
errSohail Shah; Anshul Kamboj; Kourtney Wright; Daniele Salvato; Arnold Pradhan; Daniel J. Murray; Luca Capriotti; Tiankai Yao; Mukesh N. Bachhav
err分享
err收藏
Chemical Interaction of Palladium in Uranium Oxycarbide Nuclear Fuel Kernel
errMicroscopy and Microanalysis
IF3
err2025-07-25
err0
PREAI
errJana Howard; Guang Yang; Haiyan Zhao; Patrick Warren; Tiankai Yao; Steven Cavazos; Elizabeth Sooby Wood
err分享
err收藏
Microstructural Analysis of Silicon Carbide Cladding Using 4-Dimensional Scanning Transmission Electron Microscopy
errMicroscopy and Microanalysis
IF3
err2025-07-25
err0
PREAI
errGuang Yang; Tiankai Yao; Fei Xu; Peng Xu; Sean Gonderman; Jack Gazza
err分享
err收藏
Advanced Interactive 3D Visualization Tool for Customizable Analysis of Tomography Datasets in Materials Science
errMicroscopy and Microanalysis
IF3
err2025-07-25
err0
PREAI
errStacey Whitmore; Rajiv Khadka; Xingyue Yang; Fei Xu; Tiankai Yao
err分享
err收藏
Accurate segmentation of localized corrosion in structural alloys via deep learning基于深度学习的结构合金局部腐蚀的精确分割
errnpj Materials Degradation
IF7.6
err2025-07-03
err0
errOAAI
errLiang Zhao; Jenifer Locke; Fei Xu; Tiankai Yao; Xiaolei Guo
err分享
err收藏
Local chemical ordering of a neutron-irradiated CrFeMnNi compositionally complex alloy中子辐照的CrFeMnNi成分复杂合金的局部化学有序性
errACTA MATERIALIA
IF9.3
err2025-03-01
err0
PREAI
errCurtis, Nathan; Shah, Sohail; Bachhav, Mukesh; Bawane, Kaustubh; Teng, Fei; Parkin, Calvin; Yao, Tiankai; Wen, Haiming; Couet, Adrien
err分享
err收藏
Transmission Electron Microscopy Characterization of Fuel Cladding Chemical Interaction between Minor Actinides bearing U-Pu-Zr Fuel and AIM1 Cladding透射电子显微镜表征含少量锕系元素U-Pu-Zr燃料与AIM1包壳之间的化学相互作用
errJOURNAL OF NUCLEAR MATERIALS
IF3.2
err2025-03-01
err0
PREAI
errChen, Di; Burns, Jatuporn; Wright, Karen E.; Salvato, Daniele; Yao, Tiankai; Capriotti, Luca
err分享
err收藏
Extrusion-based additive manufacturing of zirconium carbide for nuclear fuel cell structures
errCERAMICS INTERNATIONAL
IF5.6
err2025-01-01
err0
PREAI
errYang, Guang; Xiang, Yuhui; Poirier, Thomas; Malmir, Narges; Yao, Tiankai; Churi, Nikhil; Taylor, Brian; Edgar, James H.; Lin, Dong; Lei, Shuting
err分享
err收藏

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