Education

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

Research Interests

• 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

Selected Publications

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).