Previous Experience
- 2011 - 2012, Research Associate, Nuclear Systems Design and Analysis Group, Los Alamos National Laboratory.
- 2006 - 2010, Research Assistant, Purdue University.
Journal
- Wei, Jie. , Li, Song. , Zhou, Wei. , Shen, Pei. , Ren, Shuai. , Hu, Alice. & Zhou, Wenzhong*. (2019). First principles investigation of water adsorption on FeCrAl (110) surfaces. Applied Surface Science. 465 (2019). 259 - 266. doi:10.1016/j.apsusc.2018.09.202
- Shen, Pei. , Zhou, Wenzhong*. , Cassiaut-Louis, Nathalie. , Journeau, Christophe. , Piluso, Pascal. & Liao, Yehong. (2018). Corium behavior and steam explosion risks: A review of experiments. Annals of Nuclear Energy. 121. 162 - 176.
- Zhou, Wei. & Zhou, Wenzhong*. (2018). Enhanced Thermal Conductivity Accident Tolerant Fuels for Improved Reactor Safety - A Comprehensive Review. Annals of Nuclear Energy. 119(2018). 66 - 86.
- Liu, Rong. , Zhou, Wenzhong*. & Cai, Jiejin*. (2018). Multiphysics modeling of accident tolerant fuel-cladding combination U3Si2-FeCrAl performance in a light water reactor. Nuclear Engineering and Design. 330(2018). 106 - 116.
- Zhou, Wei. & Zhou, Wenzhong*. (2018). Thermophysical and mechanical analyses of UO2-36.4 vol% BeO fuel pellets with Zircaloy, SiC, and FeCrAl claddings. Metals. 8/1. 1 - 14. doi:10.3390/met8010065
- Zhou, Wenzhong*. , Revankar, Shripad. T. , Liu, Rong. & Shahmohammadi Beni, Mehrdad. (2017). Microstructure Based Thermal Conductivity and Thermal Behavior Modeling of Nuclear Fuel UO2-BeO. Heat Transfer Engineering. 0. 1 - 15.
- Liu, Rong. & Zhou, Wenzhong*. (2017). Multiphysics modeling of novel UO2-BeO sandwich fuel performance in a light water reactor. Annals of Nuclear Energy. 109. 298 - 309.
- Liu, Rong. , Zhou, Wenzhong*. & Zhou, Wei. (2016). Fully coupled modeling of burnup-dependent (U1-y, Puy)O2-x mixed oxide fast reactor fuels performance. Metallurgical and Materials Transactions E: Materials for Energy Systems. doi:10.1007/s40553-015-0065-6
- Liu, Rong. , Prudil, Andrew. , Zhou, Wenzhong*. & Chan, Paul. K. (2016). Multiphysics Coupled Modeling of Light Water Reactor Fuel Performance. Progress in Nuclear Energy. 91. 38 - 48.
- Liu, Rong. , Zhou, Wenzhong*. , Prudil, Andrew. & Chan, Paul. K. (2016). Multiphysics modeling of UO2-SiC composite fuel performance with enhanced thermal and mechanical properties. Applied Thermal Engineering. 107. 86 - 100.
- Zhou, Wenzhong*. , Liu, Rong. & Revankar, Shripad. T. (2015). Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2-BeO fuel in light water reactors. Annals of Nuclear Energy. 81. 240 - 248.
- Liu, Rong. , Zhou, Wenzhong*. , Shen, Pei. , Prudil, A. & Chan, P.K. (2015). Fully Coupled Multiphysics Modeling of Enhanced Thermal Conductivity UO2-BeO Fuel Performance in a Light Water Reactor. Nuclear Engineering and Design. 295. 511 - 523.
- Zhou, Wenzhong*. & Liu, Rong. (2015). Fully Coupled Simulation of Oxygen and Heat Diffusion for (U, Pu)O2 Fuel in Both FBR and LWR. The ASME Journal of Nuclear Engineering and Radiation Science. 1/4. doi:10.1115/1.4031033
- Revankar, Shripad. T. & Zhou, Wenzhong. (2015). Performance of Vertical Tube Passive Condenser with the Effects of Noncondensable and Secondary Cooling Water. Heat Transfer Engineering. 36/4. 368 - 377.
- Hao, Chonglei. , Li, Jing. , Liu, Yuan. , Zhou, Xiaofeng. , Liu, Yahua. , Liu, Rong. , Che, lufeng. , Zhou, Wenzhong. , Li, Lawrence. , Sun, Dong. , Xu, Lei. & Wang, Zuankai. (2015). Superhydrophobic-like tunable droplet bouncing on slippery liquid interfaces. Nature Communications. 6. 7986 doi:10.1038/ncomms8986
- Revankar, Shripad. T. , Zhou, Wenzhong. & Chandramouli, Deepthi. (2015). Thermal Performance of UO2-BeO Fuel during a Loss of Coolant Accident. International Journal of Nuclear Energy Science and Engineering. 5/0. 1 - 8.
- Zhou, Wenzhong*. , Liu, Rong. & Revankar, Shripad. (2014). UO2-BeO Composite Fuel Thermal Property and Performance Modeling. Journal of Energy and Power Engineering. 8. 1183 - 1191.
- Zhou, W.*. , Wolf, B. & Revankar, S. (2013). Assessment of RELAP5/MOD3.3 condensation models for the tube bundle condensation in the PCCS of ESBWR. Nuclear Engineering and Design. 264. 111 - 118.
- Kim, Sungki. , Ko, Wonil. , Zhou, Wenzhong. , Revankar, Shripad. T. , Chung, Yanghon. & Bang, Sungsig. (2012). The Credit Analysis of Recycling Beryllium and Uranium in BeO-UO2 Nuclear Fuel. Journal of nuclear Science and Technology. 49/3. 298 - 309.
- Revankar, Shripad. T. , Oh, Seungmin. , Zhou, Wenzhong. & Henderson, Gavin. (2010). Condensation correlation for a vertical passive condenser system. Nuclear Technology. 170. 28 - 39.
- Zhou, Wenzhong. , Henderson, Gavin. & Revankar, Shripad. T. (2010). Condensation in a vertical tube bundle passive condenser - Part 1: Through flow condensation. International Journal of Heat and Mass Transfer. 53. 1146 - 1155.
- Henderson, Gavin. , Zhou, Wenzhong. & Revankar, Shripad. T. (2010). Condensation in a vertical tube bundle passive condenser- Part 2: Complete condensation. International Journal of Heat and Mass Transfer. 53. 1156 - 1163.
- Kim, S.K. , Ko, W.I. , Kim, H.D. , Revankar, S. T. , Zhou, W. & Jo, D. (2010). Cost-benefit analysis of BeO-UO2 nuclear fuel. Progress in Nuclear Energy. 52/8. 813 - 821.
- Revankar, Shripad. T. , Oh, Seungmin. , Zhou, Wenzhong. & Henderson, Gavin. (2009). Scaling of passive condenser system for separate effect testing. Nuclear Engineering and Design. 239. 1870 - 1878.
External Services
Professional Activity
- 2011 - Now, Associate Editor, Journal of Power Technologies.
- 2011 - Now, Associate Editor, Energy and Environment Research.
- 2011 - Now, Associate Editor, Mechanical Engineering Research.
- 2011 - Now, Member of Editorial Board, Modern Applied Science .
Community Service
- 2015 - Now, Member, The Minerals, Metals & Materials Society.
- 2011 - Now, Member, American Nuclear Society.
- 2011 - Now, Member, Sigma XI, The Scientific Research Society.
- 2009 - Now, Member, American Society of Mechanical Engineers.
Last update date :
27 Sep 2018
