Superhydrophobic-like tunable droplet bouncing on slippery liquid interfaces C Hao, J Li, Y Liu, X Zhou, Y Liu, R Liu, L Che, W Zhou, D Sun, L Li, L Xu, ... Nature communications 6 (1), 7986, 2015 | 287 | 2015 |
Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2–BeO fuel in light water reactors W Zhou, R Liu, ST Revankar Annals of Nuclear Energy 81, 240-248, 2015 | 54 | 2015 |
Multiphysics coupled modeling of light water reactor fuel performance R Liu, A Prudil, W Zhou, PK Chan Progress in Nuclear Energy 91, 38-48, 2016 | 46 | 2016 |
Fully coupled multiphysics modeling of enhanced thermal conductivity UO2–BeO fuel performance in a light water reactor R Liu, W Zhou, P Shen, A Prudil, PK Chan Nuclear Engineering and Design 295, 511-523, 2015 | 42 | 2015 |
Multiphysics modeling of accident tolerant fuel-cladding U3Si2-FeCrAl performance in a light water reactor R Liu, W Zhou, J Cai Nuclear Engineering and Design 330, 106-116, 2018 | 34 | 2018 |
Multiphysics modeling of UO2-SiC composite fuel performance with enhanced thermal and mechanical properties R Liu, W Zhou, A Prudil, PK Chan Applied Thermal Engineering 107, 86-100, 2016 | 31 | 2016 |
Multiphysics modeling of novel UO2-BeO sandwich fuel performance in a light water reactor R Liu, W Zhou Annals of Nuclear Energy 109, 298-309, 2017 | 24 | 2017 |
Multiphysics modeling of thorium-based fuel performance with a two-layer SiC cladding in a light water reactor R Liu, J Cai, W Zhou Annals of Nuclear Energy 136, 107036, 2020 | 21 | 2020 |
Preliminary thermal hydraulic analysis of various accident tolerant fuels and claddings for control rod ejection accidents in LWRs Z Chen, J Cai, R Liu, Y Wang Nuclear Engineering and Design 331, 282-294, 2018 | 19 | 2018 |
Microstructure-Based Thermal Conductivity and Thermal Behavior Modeling of Nuclear Fuel UO2-BeO W Zhou, ST Revankar, R Liu, MS Beni Heat Transfer Engineering 39 (9), 760-774, 2018 | 15 | 2018 |
Thermal hydraulic analysis of accident tolerant fuels for Reactivity-Initiated-Accident in PWR with different coolant channel geometries S He, J Cai, Z Chen, R Liu Nuclear Engineering and Design 351, 131-142, 2019 | 10 | 2019 |
Deuterium permeability and diffusivity in FeCrAl alloys for LWR cladding application S Gao, Z Duan, Y Wu, Y Zhou, P Chen, H Huang, Y Liu, R Liu, S Liu, ... International Journal of Hydrogen Energy 47 (46), 20323-20332, 2022 | 9 | 2022 |
Multiphysics modeling of thorium-based fuel performance with Cr-Coated SiC/SiC composite under normal and accident conditions S Liu, R Liu, C Qiu, W Zhou Frontiers in Energy Research 9, 677606, 2021 | 9 | 2021 |
Multiphysics analysis of thorium-based fuel performance under reactor normal operating and accident conditions in a light water reactor C Qiu, R Liu, J Cai, W Zhou Nuclear Engineering and Design 375, 111096, 2021 | 7 | 2021 |
Research on thermal behaviors of several accident tolerant fuels based on 5× 5 bundle subchannel model J Cai, Z Chen, S He, R Liu Annals of Nuclear Energy 133, 9-20, 2019 | 7 | 2019 |
Structural stability of Cr-related defect complex in diamond for single photon sources: A first-principles study R Liu, RY Tian, YJ Zhao Journal of Applied Physics 113 (10), 2013 | 7 | 2013 |
Multiphysics analysis of thorium-based fuel performance with a two-layer SiC cladding under normal operating and transient conditions in a light water reactor C Qiu, R Liu, J Cai, W Zhou Annals of Nuclear Energy 163, 108543, 2021 | 5 | 2021 |
UO2-BeO composite fuel thermal property and performance modeling W Zhou, R Liu, ST Revankar Journal of Energy and Power Engineering 8 (7), 2014 | 4 | 2014 |
Transient fuel behavior analysis of U3Si2 fuel and FeCrAl cladding based on multiphysics method S Liu, R Liu, C Qiu Progress in Nuclear Energy 159, 104648, 2023 | 2 | 2023 |
CAMPUS-ANNULAR: Preliminary multiphysics modeling of annular fuel performance under normal operating and accident conditions S Liu, R Liu, C Qiu Progress in Nuclear Energy 153, 104430, 2022 | 2 | 2022 |