| Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel SK Lee, M Liu, NR Brown, KA Terrani, ED Blandford, H Ban, CB Jensen, ... International Journal of Heat and Mass Transfer 132, 643-654, 2019 | 62 | 2019 |
| Potential impact of accident tolerant fuel cladding critical heat flux characteristics on the high temperature phase of reactivity initiated accidents M Liu, NR Brown, KA Terrani, AF Ali, ED Blandford, DM Wachs Annals of Nuclear Energy 110, 48-62, 2017 | 41 | 2017 |
| Development of effective thermal conductivity model for particle-type nuclear fuels randomly distributed in a matrix M Liu, Y Lee, DV Rao Journal of Nuclear Materials 508, 168-180, 2018 | 33 | 2018 |
| The role of nuclear energy in the carbon neutrality goal L Liu, H Guo, L Dai, M Liu, Y Xiao, T Cong, H Gu Progress in Nuclear Energy 162, 104772, 2023 | 32 | 2023 |
| 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 C Forsberg, D Wang, E Shwageraus, B Mays, G Parks, C Coyle, M Liu Nuclear Technology, 2019 | 26 | 2019 |
| Correlations for predicting single phase and two-phase flow pressure drop in pebble bed flow channels B Bai, M Liu, X Lv, J Yan, X Yan, Z Xiao Nuclear engineering and design 241 (12), 4767-4774, 2011 | 19 | 2011 |
| Estimation of the depressurization process of Fukushima Daiichi NPP Unit 1 with SAMPSON M Liu, Y Ishiwatari, K Okamoto Nuclear Technology 186 (2), 216-228, 2014 | 18 | 2014 |
| Unsteady numerical simulations of single-phase turbulent mixing in tight lattice geometries M Liu, Y Ishiwatari Nuclear Engineering and Design 256, 28-37, 2013 | 18 | 2013 |
| Estimation of the Depressurization Process of Fukushima Daiichi NPP Unit 1 with SAMPSON M Liu, Y Ishiwatari, K Okamoto 2012 ANS Winter Meeting and Nuclear Technology Expo: International Meeting …, 2012 | 18 | 2012 |
| Numerical investigation of transverse flow and turbulent mixing in a helical cruciform fuel bundle H Zhao, H Gu, M Liu, Y Xiao Annals of Nuclear Energy 169, 108944, 2022 | 16 | 2022 |
| Development of a RELAP5 model for the thermo-hydraulic characteristics simulation of the helically coiled tubes Z Xu, M Liu, Y Xiao, H Gu Annals of Nuclear Energy 153, 108032, 2021 | 16 | 2021 |
| Effect of heater material and thickness on the steady-state flow boiling critical heat flux SK Lee, M Liu, NR Brown, KA Terrani, Y Lee Nuclear Technology 206 (2), 339-346, 2020 | 16 | 2020 |
| Development of a two-regime heat conduction model for TRISO-based nuclear fuels M Liu, J Thurgood, Y Lee, DV Rao Journal of Nuclear Materials 519, 255-264, 2019 | 16 | 2019 |
| Experimental study on heat transfer and pressure drop characteristics in a microchannel heat exchanger assembly with S-shaped fins C Zeng, Y Song, X Zhou, F Zhang, M Jiao, M Liu, H Gu Applied Thermal Engineering 210, 118406, 2022 | 15 | 2022 |
| Experimental investigation on heat transfer to supercritical water in a three-rod bundle with spacer grids S Chen, H Gu, M Liu, Y Xiao, D Cui Applied Thermal Engineering 164, 114466, 2020 | 15 | 2020 |
| Unsteady numerical simulations of the single-phase turbulent mixing between two channels connected by a narrow gap M Liu, Y Ishiwatari Nuclear engineering and design 241 (10), 4194-4205, 2011 | 14 | 2011 |
| Experimental and numerical study of the thermal hydraulics characteristics of a helical-coiled once-through steam generator Z Xu, M Chao, W Zhang, F Zhang, Y Xiao, M Liu, H Gu Applied Thermal Engineering 217, 119117, 2022 | 12 | 2022 |
| Diagnosis of break size and location in LOCA and SGTR accidents using support vector machines M Liu, L Wang, Y Lee Progress in Nuclear Energy 140, 103902, 2021 | 12 | 2021 |
| Optimization of the TRISO fuel particle distribution based on octahedral and icosahedral-based segmentation methods in the pebble-bed nuclear core M Liu, C Zeng, Z Luo, H Gu, J Deng International Journal of Advanced Nuclear Reactor Design and Technology 2 …, 2020 | 12 | 2020 |
| Influence of helix angle on flow and heat transfer characteristics of lead–bismuth flow in helical-coiled tube bundles C Shen, L Liu, Z Xu, H Gu, M Liu Annals of Nuclear Energy 180, 109483, 2023 | 11 | 2023 |
Nicholas R. BrownProfessor and Pietro F. Pasqua Fellow在 utk.edu 的电子邮件经过验证
