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Weiqian Zhuo
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Impurity driven corrosion behavior of HAYNES® 230® alloy in molten chloride Salt
B D’Souza, W Zhuo, Q Yang, A Leong, J Zhang
Corrosion Science 187, 109483, 2021
292021
Europium induced alloy corrosion and cracking in molten chloride media for nuclear applications
S Guo, W Zhuo, Y Wang, J Zhang
Corrosion Science 163, 108279, 2020
222020
Electrochemical extraction of lanthanum in molten fluoride salts assisted by KF or NaF
Y Wang, J Ge, W Zhuo, S Guo, J Zhang
Electrochemistry Communications 104, 106468, 2019
172019
Selective electrodeposition of europium and samarium in molten LiCl-KCl with copper and aluminum electrodes
J Ge, Q Yang, Y Wang, W Zhuo, M Du, J Zhang
Journal of The Electrochemical Society 167 (2), 022501, 2020
142020
Electrochemical separation study of LaF3 in molten FLiNaK salt
Y Wang, J Ge, W Zhuo, S Guo, J Zhang
Journal of Nuclear Materials 518, 162-165, 2019
142019
XRD and SEM/EDS characterization of two quaternary fuel alloys (U-2.5 Mo-2.5 Ti-5.0 Zr and U-1.5 Mo-1.5 Ti-7.0 Zr in wt.%) for fast reactors
W Zhuo, Y Xie, MT Benson, J Ge, RD Mariani, J Zhang
Materials Characterization 170, 110696, 2020
122020
Effect of neighboring wall on the fluid added mass of CAP1400 spent fuel storage rack
Y Liu, D Lu, W Li, W Zhuo
Progress in Nuclear Energy 101, 177-187, 2017
122017
The studies of mixing and thermal stratification in SMR containments
F Niu, W Zhuo, J Cai, X Su, Y Hu, Y Zhao, T Ma, Y Wang, Y Yu
Nuclear Engineering and Design 298, 14-24, 2016
122016
Experimental and CFD analysis of the effects of debris deposition across the fuel assemblies
MS Azam, F Niu, D Wang, W Zhuo
Nuclear Engineering and Design 332, 238-251, 2018
112018
Hermeticity and tensile experiment of small plate-type SiC ceramic composites for advanced reactor applications
W Zhuo, F Niu, Y Zhao, J Liu
Annals of Nuclear Energy 110, 1098-1106, 2017
82017
Experimental investigation of FCCI using diffusion couple test between UZr fuel with Sb additive and cladding
W Zhuo, Y Xie, MT Benson, Q Yang, RD Mariani, J Zhang
Nuclear Science and Engineering 194 (6), 462-476, 2020
72020
Experimental analysis of steam mixing and thermal stratification phenomena related to small steel containment studies
S Wang, Y Wang, W Zhuo, F Niu, Y Yu, Z Guo, Y Shen, W Chen, X Jiang
Annals of Nuclear Energy 109, 103-112, 2017
72017
Influence of injection temperature and flow rate on mixing and stratification in small passively cooling enclosures
WQ Zhuo, FL Niu, JC Cai, XW Su, YQ Hu, YG Zhao, Y Yu
Nuclear Science and Techniques 27, 1-11, 2016
62016
Modeling and experimental studies on air buoyant jets for application to small containments
T Ma, F Niu, W Zhuo, Y Wang, T Warraich, S Azam
Annals of Nuclear Energy 109, 212-219, 2017
52017
Experimental assessment of antimony (Sb) in pure uranium for immobilizing fission product lanthanides
W Zhuo, Y Xie, MT Benson, H Wu, RD Mariani, J Zhang
Journal of Nuclear Materials 534, 152135, 2020
42020
Aluminum alloy corrosion and precipitation in high-temperature flow loop simulating environment after loss-of-coolant accidents
D Wang, A Leong, W Zhuo, H Wu, Q Yang, J Zhang
Journal of Alloys and Compounds 896, 163035, 2022
32022
Solid-state phase transitions of two quaternary metallic fuel alloys (U-2.5 Mo-2.5 Ti-5.0 Zr and U-1.5 Mo-1.5 Ti-7.0 Zr in wt.%)
W Zhuo, H Wu, Y Xie, MT Benson, J Zhang
Journal of Nuclear Materials 555, 153134, 2021
32021
The formation mechanism of the Zr rind in U-Zr fuels
MT Benson, T Yao, JN Zelina, F Teng, D Murray, F Di Lemma, ...
Journal of Nuclear Materials 572, 154057, 2022
22022
Assessment of head loss through LOCA-generated debris deposited in PWR fuel assemblies
D Wang, F Niu, R Liang, W Zhuo, S Wang
Annals of Nuclear Energy 137, 107037, 2020
22020
Young’s Modulus and Gas Tightness Measurement of Ceramic Matrix Composite-SiC for Advanced Reactor Application
Y Zhao, F Niu, Y Yu, W Zhuo, Z Hao, W Xiao
International Conference on Nuclear Engineering 55782, V001T02A017, 2013
22013
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