Ph.D, Aerospace Engineering, University of Florida, 2000 - 2005
Master of Science, Xi'an Jiaotong University, 1997
Bachelor of Engineering, Huazhong University of Science and Technology, 1994
Liao, J., Ferroni, P., Wright, R.F., Bachrach, U., Scobel, J.H., Sofu, T., Tentner, A.M., Lee, S.J., Epstein, M., Frignani, M., & Tarantino, M. (2021). Development of phenomena identification and ranking table for Westinghouse lead fast reactor's safety. PROGRESS IN NUCLEAR ENERGY, 131, 103577.Elsevier. doi: 10.1016/j.pnucene.2020.103577.
Hua, T.Q., Lee, S.J., Liao, J., Moisseytsev, A., Ferroni, P., Karahan, A., Paik, C.Y., Tentner, A.M., & Sofu, T. (2020). Development of Mechanistic Source Term Analysis Tool SAS4A-FATE for Lead- and Sodium-Cooled Fast Reactors. Nuclear Technology, 206(2), 206-217.Taylor & Francis. doi: 10.1080/00295450.2019.1598715.
Liao, J., & Utley, D. (2020). Study on Reactor Vessel Air Cooling for Westinghouse Lead Fast Reactor. Nuclear Technology, 206(2), 191-205.Taylor & Francis. doi: 10.1080/00295450.2019.1599614.
Liao, J., Ohkawa, K., Brown, W.L., & Wright, R.F. (2019). A Study on Onset of Liquid Entrainment in Low Pressure Depressurization System of Advanced Passive Pressurized Water Reactors. Journal of Nuclear Engineering and Radiation Science, 5(4).ASME International. doi: 10.1115/1.4042796.
Liao, J. (2016). System scaling analysis for modeling small break LOCA using the FULL SPECTRUM LOCA evaluation model. ANNALS OF NUCLEAR ENERGY, 87, 443-453.Elsevier. doi: 10.1016/j.anucene.2015.09.014.
Liao, J., Kucukboyaci, V.N., & Wright, R.F. (2016). Development of a LOCA safety analysis evaluation model for the Westinghouse Small Modular Reactor. Annals of Nuclear Energy, 98, 61-73.Elsevier. doi: 10.1016/j.anucene.2016.07.023.
Liao, J., Frepolil, C., & Ohkawa, K. (2015). Cold leg condensation model for analyzing loss-of-coolant accident in PWR. NUCLEAR ENGINEERING AND DESIGN, 285, 171-187.Elsevier. doi: 10.1016/j.nucengdes.2015.01.011.
Liao, J.Liao, J. (2015). A Horizontal Stratified Gas-Liquid Two-Phase Flow Model for the Two-Fluid Model in the WCOBRA/TRAC-TF2 PWR Safety Analysis Code. Nuclear Engineering and Design, 295, 239-250.
Liao, J., Mei, R., & Klausner, J.F. (2008). A study on the numerical stability of the two-fluid model near ill-posedness. International Journal of Multiphase Flow, 34(11), 1067-1087.Elsevier. doi: 10.1016/j.ijmultiphaseflow.2008.02.010.
Liao, J., Mei, R., & Klausner, J.F. (2006). A film boiling model for cryogenic chilldown at low mass flux inside a horizontal pipeline. Heat and Mass Transfer, 42(10), 891-900.Springer Nature. doi: 10.1007/s00231-006-0143-5.
Liao, J., Mei, R., & Klausner, J.F. (2004). The influence of the bulk liquid thermal boundary layer on saturated nucleate boiling. International Journal of Heat and Fluid Flow, 25(2), 196-208.Elsevier. doi: 10.1016/j.ijheatfluidflow.2003.11.012.
Liao, J. (2019). Importance of PIRT to the Safety of Heat Pipe Based Micro Nuclear Reactor. In ANS Winter Meeting.ANS.Washington DC.
Liao, J. (2019). Data-Driven Safety Margin Management using Reduced Order Modeling. In ANS Winter Meeting.ANS.Washington DC.
Liao, J. (2019). The Westinghouse Lead Fast Reactor Program. In Top Fuel/GLOBAL.Seattle, WA.
Liao, J. (2019). The Importance of Phenomena Identification and Ranking Table in Lead Fast Reactor Development. In 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics.Portland, USA.
Liao, J. (2019). Chromium-Coated Cladding Effects in the Context of 10 CFR 50.46c. In Top Fuel/GLOBAL.Seattle, USA.