Basic Information

Prof. Shaoqiang Guo

Department of Nuclear Science and Technology

School of Energy and Power Engineering

Xi'an Jiaotong University

Research Interests

  • Corrosion control and materials development in Advanced Nuclear Reactors
  • Pyroprocessing of Spent Nuclear Fuels

Contact

Shaoqiang Guo

Address: No. 28 Xianing West Road, Xi'an, Shaanxi, 710049, P.R. China

Email: guos2019@mail.xjtu.edu.cn

 

 

Education

B.E. in Material Science and Engineering, Univerisity of Science and Technology Beijing, 2009

Ph.D. in Material Science and Engineering, Univerisity of Science and Technology Beijing, 2014

Professional Experience

2019/01 - present Xi'an Jiaotong University, Professor

2016/12 - 2018/12 Virginia Tech, Research Scientist

2015/01 - 2016/12 The Ohio State University, Postdoctoral Researcher

2013/03 - 2015/01 Ohio University, Research Scholar

 

Publications

Selected Journal Articles

[1]   SGuo*, J. Zhang*, W. Wu, W. Zhou, Corrosion in the Molten Fluoride and Chloride Salts and Materials Development for Nuclear Applications, Progress in Materials Science, 97 (2018): 448-487.

[2]   S. Guo, L. Xu*, L. Zhang, W. Chang, X. Lu, Characterization of Corrosion Scale Formed on 3Cr Steel in CO2-saturated Formation Water, Corrosion Science, 110 (2016): 123-133.

[3]   S. Guo, J.J. Leavitt, X. Zhou, Y. Xie, S. Tietze, Y. Zhu, A. Lawver, E. Lahti, J. Zhang*, Effects of Flow, Si Inhibition, and Concurrent Corrosion of Dissimilar Metals on the Corrosion of Aluminium in the Environment Following a Loss-of-Coolant Accident, Corrosion Science, 128 (2017): 100-109.

[4]   S. Guo, B. Dsouza, Y. Xie, A. Leong, J.J. Leavitt, J. Zhang*, Aluminum corrosion in reactor containment environment following a loss of coolant accident (LOCA): High-temperature flow loop tests, Corrosion Science, 151 (2019): 122-131.

[5]     S. Guo, E. Wu, J. Zhang*, Exchange Current Density of Gd(III)/Gd Reaction in LiCl-KCl Eutectic and Analysis of Errors Caused by Various Methods, Electrochimica Acta, 259 (2018) 253-261.

[6]     S. Guo, N. Shay, Y. Wang, W. Zhou, J. Zhang*, Measurement of Europium (III)/Europium (II) Couple in Fluoride Molten Salt for Redox Control in a Molten Salt Reactor Concept, Journal of Nuclear Materials, 496 (2017): 197-206.

[7]     S. Guo, E. Wu, J. Zhang*, Investigation of electrochemical kinetics for La(III)/La reaction in molten LiCl KCl eutectic salt using potentiometric polarization, Journal of Nuclear Materials, 510(2018): 414-420.

[8]     S. Guo, J.J. Leavitt, X. Zhou, J. Zhang*, Corrosion of Aluminum Alloy 1100 in Post-LOCA Solutions of a Nuclear Reactor, RSC Advances, 6 (2016): 44119-44128.

[9]     S. Guo, F. Farelas, M. Singer*, A Glycol/Water Co-condensation Model to Investigate the Influence of Monoethylene Glycol on Top of the Line Corrosion, Corrosion, 73 (2017): 742-755.

[10]  W. Wu, S. Guo*, J. Zhang*, Exchange current densities and charge-transfer coefficients of chromium and iron dissolution in molten LiF-NaF-KF eutectic, Journal of The Electrochemical Society, 164 (2017) C840-C844.

[11]  Y. Wang, W. Zhou, S. Guo*, J. Zhang*, Thermodynamic properties of fission products (Pr, Ce, Er) in liquid bismuth by thermodynamic assessment, Journal of Nuclear Materials, 495 (2017): 181-191.

[12]  R. Chesser, S. Guo*, J. Zhang*, Electrochemical Behavior of Dysprosium and Lanthanum in Molten LiF-NaF-KF (Flinak) Salt, Annals of Nuclear Energy, 120 (2018) 246-252.

[13]  Y. Wang, W. Zhou, S. Guo*, J. Zhang*, Concentration-dependent Activity Coefficients of Lanthanides in Liquid Bismuth for the FHR Primary Coolant Cleanup, Annals of Nuclear Energy, 113 (2018) 253-261.

[14]  J. Zhang*, C.W. Forsberg, S.T. Lam, S. Guo, M.F. Simpson, R.O. Scarlat, F. Carotti, K. Chan, P. Singh, W. Doniger, K. Sridharan, J.R. Keiser, Redox Potential Control in Molten Salt Systems for Corrosion Mitigation, Corrosion Science, 144 (2018): 44-53.

[15]  M. Gonzalez, A. Burak, S. Guo, M.F. Simpon, Identification, measurement, and mitigation of key impurities in LiCl-Li2O used for direct electrolytic reduction of UO2, Journal of Nuclear Materials, 510 (2018): 513-523