Dr. Jun Wang

University of Wisconsin Madison, USA



2015 Ph.D., Xi’an Jiaotong University

Publications (Selected)

  1. J., Wang, H.J., Jo, M.L., Corradini, et al., 2018, “Potential Recovery Actions from a Severe Accident in a PWR: MELCOR Analysis of a Station Blackout Scenario”, Nuclear Technology, Accepted.
  2. J., Wang, M.L., Corradini, et al., 2018, “Iron-Chromium-Aluminum (FeCrAl) Cladding Oxidation kenetics and Auxiliary Feedwater Sensitivity Analysis: Short-Term Station Blackout Simulation of Surry Nuclear Power Plant”, ASME Journal of Nuclear Engineering and Radiation Science, Accepted.
  3. J., Wang, M., Mccabe, M.L., Corradini, et al., 2017, “Accident Tolerant Clad Material Modeling by MELCOR: Benchmark for SURRY Short Term Station Blackout”, Nuclear Engineering and Design, Volume 313, Pages 458–469. (SCI: EP4OM; EI: 20170303252002).
  4. J., Wang, C., Wang, M.L., Corradini, et al., 2016, “PHEBUS FPT-1 Simulation by using MELCOR and Primary Blockage Model Exploration”, Nuclear Engineering and Design, Vol.307, PP.119-129. (SCI: DW7IM; EI: 20163002633624).
  5. J., Wang, Y.Q., Fan, Y.P., Zhang, et al., 2016, “The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant C 6.
  6. J., Wang, M.L., Corradini, W., F., et al., 2015, “Simulation of the PHEBUS FPT-1 Experiment Using MELCOR and Exploration of the Primary Core Degradation Mechanism”, Annals of Nuclear Energy, Vol.85, PP.193-204(SCI: CR5VZ; EI: 20152300911990).
  7. J., Wang, M.L., Corradini, T., Haskin, et al., 2015, “Comparison of Hydrogen Generation Rate between CORA-13 Test and MELCOR Simulation: Clad Solid-Phase Oxidation Models using Self-Developed Code MYCOAC”, Nuclear Technology, Vol.192, No.1, PP.25-34 (SCI: CT2FK; EI: 20155201728364).
  8. J., Wang, M.L., Corradini, W., Fu, et al., 2014, “Comparison of CORA & MELCOR Core Degradation Simulation and THE MELCOR Oxidation Model”, Nuclear Engineering and Design, Vol.276, PP.191-201(SCI: AO0CM; EI: 20142917941891).
  9. J., Wang, C., Wang, K.Y., Shi, et al., 2018. Review on Core Degradation and Material Migration Research in Light Water Reactors. Frontiers in Energy Research. doi: 10.3389/fenrg.2018.00003 (EI: 20181004862317).
  10. J., Wang, W.X., Tian, J.N., Lu, et al., 2014. Development of In-vessel Severe Accident Analysis Code Oxidation Module MIDAC-OX. Atomic Energy Science and Technology, Vol.48, No.8, PP.1440-1447. (EI: 20143700064329).
  11. J., Wang, Y.P., Zhang, K.Y., Mao, et al., 2014, “MELCOR Simulation of Core Thermal Response during a Station Blackout Initiated Severe Accident in China Pressurized Reactor (CPR1000)”, Progress in Nuclear Energy, Vol.81, 6-15(SCI: CG2FN; EI: 20150300425023).
  12. J., Wang, W.X., Tian, Y.P., Zhang, et al., 2014, “The Development of Module In-vessel Degraded Severe Accident Analysis Code MIDAC and the Relevant Research for CPR1000 during the Station Blackout Scenario”, Progress in Nuclear Energy, Vol.76, PP.44-54(SCI: AM1IQ; EI: 20142517830559).
  13. J., Wang, W.X., Tian, K., Feng, et al., 2013, “Development of CHF Models for inner and outer RPV Gaps in a Meltdown Severe Accident”, Nuclear Engineering and Design, Vol.265, PP.1045-1056(SCI: 294ZD; EI: 20134716995873).
  14. J., Wang, K.Y., Shi, Z.M., Meng, R., Shripad, 2018 “Nuclear Thermal Hydraulic and Two-Phase Flow”, Lausanne, Switzerland, Frontiers.
  15. R., Daily, J., Wang, M.L., Corradini, Light Water Reactor Sustainability Program, Generic Boiling Water Reactor MELCOR Plant Model, U.S. Department of Energy, Office of Nuclear Energy, Washington, DC, United States.