Guiqiu (Tony) Zheng
Ph.D. Materials Science, University of Wisconsin-Madison, 2015
M.S. Materials Science, University of Wisconsin-Madison, 2012
M.S. Biomedical Engineering, Sichuan University, China, 2007
B.S. Materials Science and Engineering, Chengdu University of Technology, China, 2004
- Nuclear materials development for Fluoride salt-cooled High-temperature Reactor (FHR)
- Tritium behavior in neutron irradiated molten salts and structural materials
- Microstructural characterization of irradiated and non-irradiated
- In-core experiments and post-irradiation examination (PIE)
- Molten salts chemistry and high-temperature corrosion
Corrosion-induced microstructural development in 316 stainless steel during exposure to molten Li2BeF4 (FLiBe) sal, G. Zheng, L. He, D. Carpenter, and K. Sridharan, Journal of Nuclear Materials 482, 147-155(2016).
High temperature corrosion of structural alloys in molten Li2BeF4 (FLiBe) salt, G. Zheng, D. Carpenter, L. Hu, and K. Sridharan, Advances in Materials Science for Environmental and Energy Technologies V: Ceramic Transactions 260, 93-101(2016).
Microstructural Characterization of In-reactor Corrosion Tested Hastelloy N® and 316 Stainless Steel, G. Zheng, D. Carpenter, M. Ames, Y. Ostrovsky, G. Kohse, K. Sun, and L. Hu, Transactions of the American Nuclear Society 114, 1104-1105(2016).
High Temperature Corrosion of Hastelloy N in Molten Li2BeF4 (FLiBe) Salt, G. Zheng, B. Kelleher, G. Cao, M. Anderson, K. Sridharan, and T. R. Allen, Corrosion, 71, 1257-1266 (2015).
Corrosion of 316 Stainless Steel in High Temperature Molten Li2BeF4 (FLiBe) Salt, G. Zheng, B. Kelleher, G. Cao, M. Anderson, K. Sridharan, and T. R. Allen, Journal of Nuclear Materials 461, 143-150 (2015).
Advanced Heat Exchanger Development for Molten Salts, P. Sabharwall, D. Clark, M. Glazoff, G. Zheng, K. Sridharan, and M. Anderson, Nuclear Engineering and Design 280, 42-56 (2014).
Effect of Exposure Environment on Surface Decomposition of SiC-Silver Ion Implantation Diffusion Couples, T. J. Gerczak, G. Zheng, K. G. Field, and T. R. Allen, Journal of Nuclear Materials 456, 281-286 (2015).
Characterization of Structural Defects in Nuclear Graphite IG-110 and NBG-18, G. Zheng, P. Xu, K. Sridharan, and T. R. Allen, Journal of Nuclear Materials 446, 193-199 (2014).
Investigation of 2LiF-BeF2 (FLiBe): Salt Transfer, Corrosion Tests and Characterization, G. Zheng, B. Kelleher, G. Cao, K. Sridharan, M. Anderson, and T. R. Allen, Transactions of the American Nuclear Society 109, 259-260 (2013).
Pore Structure Analysis of Nuclear Graphite IG-110 and NBG-18, G. Zheng, P. Xu, K. Sridharan, and T. R. Allen, Advances in Materials Science for Environmental and Nuclear Technology II: Ceramic Transactions 227, 251-260 (2011).
Structural Characteristics of Poly(vinyl alcohol)-Calcium Carbonate Composites Prepared by Sequential Method, G. Zheng, X. Li, X. Wang, J. Ma, and Z. Gu, Advances in Applied Ceramics 107(1), 46-51 (2008).
Synthesis of Hydroxyapatite in Polymeric Solutions for Organic-Inorganic Nanocomposites, G. Zheng, X. Li, X. Wang, S. Yu, Z. Gu, and X. Zhang, Key Engineering Materials 330-332, 427-430 (2007).