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Improvement of buoyancy and acceleration parameters for forced and mixed convective heat transfer to supercritical fluids flowing in vertical tubes
- Liu Sheng-hui, Y. Huang, Guangxu Liu, Junfeng Wang, L. K. Leung
- Materials Science
- 1 March 2017
Abstract An analytical approach is applied to examine the buoyancy and acceleration effects on forced and mixed convective heat transfer at supercritical pressures. Two non-dimensional parameters… Expand
Comparison of CHF measurements in horizontal and vertical tubes cooled with R-134a
- I. Pioro, D. C. Groeneveld, +6 authors A. Vasić
- Materials Science
- 1 October 2002
An experimental study of the critical heat flux (CHF) in horizontal and vertical tubes cooled with R-134a has been completed. The investigated ranges of flow parameters in R-134a were outlet… Expand
A review on recent heat transfer studies to supercritical pressure water in channels
- H. Wang, L. K. Leung, Weishu Wang, Qincheng Bi
- Environmental Science
- 1 September 2018
Abstract Recent studies on heat transfer to super-critical water (SCW) in tubes, annuli and rod bundles have been reviewed in support of the development of supercritical water-cooled reactors.… Expand
Numerical investigation of buoyancy effect on heat transfer to carbon dioxide flow in a tube at supercritical pressures
- Liu Sheng-hui, Y. Huang, Junfeng Wang, L. K. Leung
- 1 February 2018
Abstract A numerical analysis of the buoyancy effect on heat transfer to carbon dioxide flow at supercritical pressures in a vertical heated tube has been carried out using the FLUENT computational… Expand
Overview of methods to increase dryout power in CANDU fuel bundles
- D. C. Groeneveld, D. C. Groeneveld, L. K. Leung, J. H. Park
- Materials Science
- 1 June 2015
Abstract In CANDU reactors some degradation in the CCP (critical channel power, or power corresponding to the first occurrence of CHF in any fuel channel) will occur with time because of ageing… Expand
Thermal-hydraulics analysis of flow blockage events for fuel assembly in a sodium-cooled fast reactor
- P. Du, J. Shan, B. Zhang, L. K. Leung
- Materials Science
- 1 August 2019
Abstract The subchannel code ATHAS-LMR has been improved for analyzing thermal-hydraulics characteristics of flow blockage events in the fuel assembly of a sodium-cooled fast reactor (SFR). Based on… Expand
Heat transfer from a 2 × 2 wire-wrapped rod bundle to supercritical pressure water
- H. Wang, H. Wang, Qincheng Bi, L. K. Leung
- Materials Science
- 1 June 2016
Abstract An experiment has been completed to study the heat transfer characteristics of supercritical water in a 2 × 2 wire-wrapped rod bundle. The rod-bundle simulated a fuel assembly with four… Expand
A mechanistic bubble crowding model for predicting critical heat flux in subchannels of a bundle
- Y. Liu, W. Liu, Jianqiang Shan, Bo Zhang, L. K. Leung
- Physics
- 1 March 2020
Abstract A mechanistic model has been developed for predicting critical heat flux (CHF) in subchannels of a bundle. It is based on the bubble crowding phenomena and takes into the account of effects… Expand
An experimental and analytical study of the effect of axial power profile on CHF
- J. Yang, D. C. Groeneveld, D. C. Groeneveld, L. K. Leung, S. Cheng, M. E. Nakla
- Materials Science
- 1 July 2006
Abstract The effect of axial heat flux distribution (AFD) on the critical heat flux (CHF) was investigated. CHF measurements were obtained with HFC-134a cooled vertical tubes having four non-uniform… Expand