Dr. Jun Wang
University of Wisconsin Madison, USA
Email: jwang564@wisc.edu
Qualifications
2015 Ph.D., Xi’an Jiaotong University
Publications (Selected)
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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.
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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.
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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).
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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).
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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.
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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).
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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).
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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).
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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).
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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).
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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).
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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).
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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).
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J., Wang,
K.Y., Shi, Z.M., Meng, R., Shripad, 2018 “Nuclear Thermal Hydraulic and
Two-Phase Flow”, Lausanne, Switzerland, Frontiers.
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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.