2011年10月-2014年3月 日本东京大学 原子能国际专业博士
2009年10月-2011年9月 日本东京大学 原子能国际专业硕士
2004年9月-2008年7月 西安交通大学 核工程与核技术专业学士

2014年4月-2015年2月 日本东京大学 原子能国际专业博士后
2015年2月-2017年9月 美国新墨西哥大学博士后
2017年10月-2018年9月 美国新墨西哥大学助理研究员
2018年10月至今 上海交通大学 机械与动力工程学院 核科学与工程学院 副教授

反应堆热工水力；
核电站系统与安全、严重事故；
第四代核反应堆系统与安全；
CFD在核反应系统中的应用及验证；
两相流试验研究及先进模拟方法；
事故容错燃料；

上海市科学技术委员会，浦江计划，表面污垢对燃料临界传热及热工水力设计基准影响机理研究，2020-11至2022-10，30万元
科学技术部，国家重大课技专项子课题，可用于CAP1400 的柱塞式孔板性能试验验证，2019-1至2021-12，243.06万元

期刊文章
1. M. Liu, S. Ni, X. Wang, L. Liu, H. Gu, Experimental study on the natural circulation behavior of a full-scale PWR fuel assembly, Annals of Nuclear Energy, 174 (2022) 109172.
2. M. Liu, S. Ni, X. Wang, L. Liu, H. Gu, Development of analytical models for the natural circulation behavior of a full-scale PWR fuel assembly, Annals of Nuclear Energy, 174 (2022) 109166.
3. X. Zhou, C. Zeng, Y. Song, M. Jiao, F. Zhang, M. Liu, Experimental study on heat transfer and flow resistance performance of a microchannel heat exchanger with zigzag flow channels, Progress in Nuclear Energy, 147 (2022) 104190.
4. H. Zhao, Q. Zhang, H. Gu, Y. Xiao, M. Liu, CFD investigation on thermal-hydraulic characteristics of a helical cruciform fuel bundle, Progress in Nuclear Energy, 148 (2022) 104228.
5. H. Zhao, H. Gu, M. Liu, Y. Xiao, Numerical investigation of transverse flow and turbulent mixing in a helical cruciform fuel bundle, Annals of Nuclear Energy, 169 (2022) 108944.
6. C. Zeng, Y. Song, X. Zhou, F. Zhang, M. Jiao, M. Liu, H. Gu, Experimental study on heat transfer and pressure drop characteristics in a microchannel heat exchanger assembly with S-shaped fins, Applied Thermal Engineering, (2022) 118406.
7. C. Zeng, X. Chu, L. Liu, M. Liu, H. Gu, Performance evaluation of DRACS system of molten salt reactors using a transient solidification model, Nuclear Engineering and Design, 386 (2022) 111565.
8. Z. Xu, M. Liu, C. Chen, Y. Xiao, H. Gua, Development of an analytical model for the dryout characteristic in helically coiled tubes, International Journal of Heat and Mass Transfer, 186 (2022) 122423.
9. M. Liu, C. Zeng, L. Liu, H. Gu, Evaluation of a freeze-tolerant decay heat removal system redundancy for fluoride salt-cooled high-temperature reactors (FHR), Annals of Nuclear Energy, 165 (2022) 108681.
10. M. Liu, X. Wang, S. Ni, L. Liu, H. Gu, Development of friction factor correlations for hexagonal and square bundles with rough rods based on CFD, Annals of Nuclear Energy, 174 (2022) 109163.
11. M. Liu, L. Wang, S. Ni, X. Wang, L. Liu, H. Gu, Experimental investigation on pressure drop of a PWR fuel assembly under low Re conditions, Annals of Nuclear Energy, 167 (2022) 108768.
12. J. Li, Z. Qi, K. Cao, M. Liu, Z. Yang, Y. Xiao, Z. Xiong, H. Gu, Experimental investigation on the heat removal capacity of secondary side passive residual heat removal system for an integrated reactor, Applied Thermal Engineering, 204 (2022) 117973.
13. Z. Xu, M. Liu, Y. Xiao, H. Gu, Development of a RELAP5 model for the thermo-hydraulic characteristics simulation of the helically coiled tubes, Annals of Nuclear Energy, 153 (2021) 108032.
14. S. Ni, M. Liu, H. Gu, Modeling and validation of RELAP5 for natural circulation flow in a single PWR fuel assembly, Annals of Nuclear Energy, 151 (2021) 107940.
15. M. Liu, L. Wang, Y. Lee, Diagnosis of break size and location in LOCA and SGTR accidents using support vector machines, Progress in Nuclear Energy, 140 (2021) 103902.
16. Dongjune Chang, Maolong Liu, Youho Lee, Accident diagnosis of a PWR fuel pin during unprotected loss of flow accident with support vector machine, Nuclear Engineering and Design, 352 (2019)
17. Maolong Liu, Jared Thurgood, Youho Lee, Dasari V Rao, Development of a two-regime heat conduction model for TRISO-based nuclear fuels, Journal of Nuclear Materials 519, 255-264 (2019)
18. C. Forsberg, D. Wang, E. Shwageraus, B. Mays, G. Parks, C. Coyle, M. Liu, Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Using British Advanced Gas-Cooled Reactor (AGR) Refueling Technology and Decay-Heat-Removal Systems that Prevent Salt Freezing, Nuclear Technology, 205 (2019) 1127-1142.
19. SK Lee, M Liu, NR Brown, KA Terrani, ED Blandford, H Ban, CB Jensen, Y. Lee, Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel, International Journal of Heat and Mass Transfer 132, 643-654 (2019).
20. Maolong Liu, Satbyoul Jung, Hyungdae Kim, Youho Lee, Experimental and Analytical Investigation into Boiling Induced Thermal Stress: Its Impact on the Stress State of Oxide Scales of Nuclear Components, Nuclear Engineering and Design, 341, 66-72 (2019).
21. Maolong Liu, Youho Lee, DV Rao, Development of Effective Thermal Conductivity Model for Particle-Type Nuclear Fuels Randomly Embedded in a Matrix, Journal of Nuclear Materials, 508, 168-180 (2018).
22. Maolong Liu, Joel Hughes, Amir Ali, Edward Blandford, A concept design and accident analysis of direct reactor auxiliary cooling system (DRACS) for Fluoride Salt-cooled High-Temperature Reactors (FHRs), Nuclear Engineering and Design, 335, 54-70 (2018).
23. Maolong Liu, Nicholas Brown, Kurt Terrani, Amir Ali, Edward Blandford, Daniel Wachs, Potential impact of accident tolerant fuel cladding critical heat flux characteristics on the high temperature phase of reactivity initiated accidents, Annals of Nuclear Energy, 110, 48-62 (2017).
24. M. Liu, N. Erkan, Y. Ishiwatari, K. Okamoto, Passive depressurization accident management strategy for boiling water reactors, Nuclear Engineering and Design, 284, 176-184 (2015).
25. M. Liu, Y. Ishiwatari and K. Okamoto, Estimation of the Depressurization Process of Fukushima Dai-ichi NPP Unit 1 with SAMPSON, Nuclear Technology, 186, 216-228 (2014).
26. M. Liu, Y. Ishiwatari and K. Okamoto, Estimation of the depressurization process of Fukushima Daiichi NPP Unit 1, Japanese Journal of Multiphase Flow, 27 (3), 298-305 (2013).
27. M. Liu and Y. Ishiwatari, Unsteady numerical simulations of single-phase turbulent mixing in tight lattice geometries, Nuclear Engineering and Design, 256, 28-37 (2013).
28. K. Kawahara, Y. Ishiwatari, and M. Liu, Development of simple success criteria regarding alternative water injection for emergency response to long-term station blackout of BWR, Journal of Nuclear Science and Technology, 50, 201-211 (2013).
29. M. Liu, Y. Ishiwatari, Unsteady numerical simulations of the single-phase turbulent mixing between two channels connected by a narrow gap. Nuclear Engineering and Design, 241, 4194-4205 (2011).
30. B. Bai, M. Liu, et al., Correlations for predicting single phase and two-phase flow pressure drop in pebble bed flow channels, Nuclear Engineering and Design, 241, 4767–4774 (2011).
31. B. Bai, M. Liu, W. Su, X. Zhang, An Experimental Study on Air-Water Two-Phase Flow Patterns in Pebble Beds. Journal of Engineering for Gas Turbines and Power, 132, 042903: 1-5 (2010).

国际会议文章
1. Seong Gu Kim, Maolong Liu, Youho Lee, Jeong II Lee, Heat transfer distribution of randomly packed pebble-bed fuels for Fluoride Salt-cooled High Temperature Reactor (FHR), ATH 2018, 11-15 November, Orlando (USA)
2. Soon K. Lee, Maolong Liu, Edward D. Blandford, Youho Lee, Comparison of steady-state and transient condition flow boiling critical heat flux (CHF) of FeCrAl alloy, Zircaloy-4 and Inconel 600, ATH 2018, 11-15 November, Orlando (USA)
3. Maolong Liu, Jared Thurgood, Youho Lee, Dasari V. Rao, Development of effective thermal conductivity model for FCM and pebble fuels with randomly distributed TRISO particles, NuMat 2018, 14-18 October, Seattle (USA)
4. Charles Forsberg, Dean Wang, Eugene Shwageraus, Brian Mays, Geoff Parks, Carolyn Coyle, Maolong Liu, FLUORIDE-SALT-COOLED HIGH-TEMPERATURE REACTOR (FHR) USING BRITISH ADVANCED GAS-COOLED REACTOR (AGR) GEOMETRY AND REFUELING TECHNOLOGY, 2018 Pacific Basin Nuclear Conference, September 30-October 5; San Francisco, USA (2018)
5. Amir Ali, Maolong Liu, Nicholas Brow, Kurt Terrani, and Edward Blandford, SURFACE WETTABILITY MEASUREMENTS of FeCrAl ALLOYS UNDER LWR ENVIRONMENTS, NURETH 17, Xi'an, China (2017).
6. Maolong Liu, Matthew Ryals, Ali Amir, Colby Jensen, Keith Condie, John Svoboda, Robert O’Brien, Edward Blandford, Development of Electrical Capacitance Sensors for Accident Tolerant Fuel (ATF) Testing at the Transient Reactor Test (TREAT) Facility. TRTR 2016. Albuquerque, NM, USA (2016).
7. Edward Blandford, Edward Arthur, Jay Disser, Janine Lambert, Joel Hughes, Maolong Liu, Demonstration of the 3SBD Concept for the Pebble Bed Fluoride Salt-Cooled High-Temperature Reactor (PB-FHR). INMM 2016, Atlanta, Georgia USA (2016).
8. Joel Hughes, Maolong Liu, Bryan Wallace, Amir Ali, Matthew Denman, Nicolas Zweibaum, Per Peterson, Edward Blandford, On the question of decay heat removal system redundancy for Fluoride salt-cooled High-temperature Reactors (FHR). ICAPP 2016, San Francisco, CA, USA (2016).
9. M. Liu, Y. Ishiwatari, K. Okamoto, “Improvement of the SAMPSON code for BWR severe accident analysis,” Proc., 21st International Conference On Nuclear Engineering (ICONE-21), Chengdu, China, July 29-August 2 (2013)
10. M. Liu, Y. Ishiwatari, K. Okamoto, “Estimation of the depressurization process of Fukushima Daiichi NPP Unit 1 with SAMPSON,” International Meeting on Severe Accident Assessment and Management: Lessons Learned from Fukushima Dai-ichi, Embedded topical meeting of 2012 ANS Winter Meeting and Nuclear Technology Expo, Paper-5979, San Diego, USA, November 11-15 (2012)
11. M. Liu, Y. Ishiwatari, K. Okamoto, “Estimation of the depressurization process of Fukushima Daiichi NPP Unit 1 with SAMPSON,” International Workshop on Nuclear Safety and Severe Accident (NUSSA), TS-62, Beijing, China, Sept. 7-8 (2012)
12. M. Liu and Y. Ishiwatari, "CFD STUDY OF THE SINGLE-PHASE SUBCHANNEL TURBULENT MIXING IN TIGHT LATTICE GEOMETRY WITH," Proc. 5th Int. Sym. SCWR (ISSCWR-5), Paper-P110, Vancouver, Canada, March 13-16 (2011).

课程名称：《两相流与传热》 授课对象：本科生 学时数：36 学分：2

白博峰, 刘茂龙. 天然气长输管道安全投产置换计算软件, 计算机软件著作, 2008SR15575, 2008

[1] 海外高层次人才引进计划（青年项目），2020
[2] 上海市浦江人才计划（A类），2020