L.K.H. Leung

Canadian Nuclear Laboratories — Canada

Engineering · Physical Sciences

21h-index2.2kcitations84works0.02yr avg
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Research Topics

Heat transfer and supercritical fluids(48), Nuclear reactor physics and engineering(26), Nuclear Engineering Thermal-Hydraulics(23), Subcritical and Supercritical Water Processes(23), Heat Transfer and Boiling Studies(21)

Publications84 total

SuperCritical Water-cooled Reactors (SCWRs)
Elsevier eBooks·2023· 3 cited
Contributors
Elsevier eBooks·2023
Fluid-to-Fluid modelling of CHF at High-Pressure subcooled water conditions
Nuclear Engineering and Design·2021· 10 cited
Super-Critical Water-Cooled Reactor (SCWR)
Elsevier eBooks·2020· 17 cited
A phenomenological CHF model for mixing-vane spacers in a subchannel of a rod bundle
Annals of Nuclear Energy·2020· 4 cited
Understanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs) - Final Report of a Coordinated Research Project
2020· 5 cited
Assessment of a Theoretical Model for Predicting Forced Convective Critical Heat Flux in Rod Bundles
Frontiers in Energy Research·2019· 5 citedOpen Access
A mechanistic bubble crowding model for predicting critical heat flux in subchannels of a bundle
Annals of Nuclear Energy·2019· 21 cited
Thermal-hydraulics analysis of flow blockage events for fuel assembly in a sodium-cooled fast reactor
International Journal of Heat and Mass Transfer·2019· 15 cited
Numerical investigation of buoyancy effect on heat transfer to carbon dioxide flow in a tube at supercritical pressures
International Journal of Heat and Mass Transfer·2017· 51 cited
Assessment of Convective Heat Transfer Correlations Against an Expanded Database for Different Fluids at Supercritical Pressures
Journal of Nuclear Engineering and Radiation Science·2017· 21 cited
Nonuniform heat transfer of supercritical water in a tight rod bundle – Assessment of correlations
Annals of Nuclear Energy·2017· 17 cited
A predictive-corrective process for predicting forced convective heat transfer in heated tubes at supercritical pressures
International Journal of Heat and Mass Transfer·2017· 3 cited
Neutron Activation Analysis of Candidate Materials for High-Temperature Reactors
2017· 1 cited
CANADIAN SUPERCRITICAL WATER-COOLED REACTOR CORE CONCEPT AND SAFETY FEATURES
CNL Nuclear Review·2016· 5 cited
SAFETY ANALYSIS OF LOSS OF COOLANT ACCIDENT EVENTS FOR THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR
CNL Nuclear Review·2016
Improvement of buoyancy and acceleration parameters for forced and mixed convective heat transfer to supercritical fluids flowing in vertical tubes
International Journal of Heat and Mass Transfer·2016· 159 cited
AN ECONOMIC ANALYSIS OF THE CANADIAN SCWR CONCEPT USING G4-ECONS
CNL Nuclear Review·2016· 4 citedOpen Access
New IAEA Coordinated Research Project on Thermal-Hydraulics of Supercritical Water Cooled Reactors
2016
EVOLUTION OF THE CANADIAN SCWR FUEL-ASSEMBLY CONCEPT AND ASSESSMENT OF THE 64 ELEMENT ASSEMBLY FOR THERMALHYDRAULIC PERFORMANCE
CNL Nuclear Review·2016· 13 citedOpen Access
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Frequent Co-authors

D.C. Groeneveld(12), R. McGrath(8), Jianqiang Shan(7), Siyuan Cheng(6), J. Ledieu(6), L. H. Wearing(5), J. A. Smerdon(5), A.Ž Vasić(4), Qincheng Bi(4), T. A. Lograsso(4), Jun Yang(3), Guangxu Liu(3), Yuting Guo(3), V. Fournée(3), Thomas S. Schulenberg(3), N. Aksan(3), Yanping Huang(3), Y.F. Rao(3), P. L. Kirillov(2), Shenghui Liu(2)