Search Results - "Leung, L.K.H."
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1
Assessment of CHF characteristics at subcooled conditions for the CANFLEX bundle
Published in Nuclear engineering and design (01-11-2013)“…Boiling-Length-Average (BLA) Critical Heat Flux (CHF) values for the CANFLEX11CANFLEX® (CANdu FLEXible) is a registered trademark of Atomic Energy of Canada…”
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2
The 1995 look-up table for critical heat flux in tubes
Published in Nuclear engineering and design (01-06-1996)“…An updated version of the look-up table for critical heat flux (CHF) has been developed jointly by AECL Research (Canada) and IPPE (Obninsk, Russia). It is…”
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3
A mechanistic bubble crowding model for predicting critical heat flux in subchannels of a bundle
Published in Annals of nuclear energy (01-03-2020)“…•A new mechanistic model has been developed for predicting CHF of a bundle.•Detailed descriptions of various models of bundle effects on CHF.•The application…”
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The 2006 CHF look-up table
Published in Nuclear engineering and design (01-09-2007)“…CHF look-up tables are used widely for the prediction of the critical heat flux (CHF). The CHF look-up table is basically a normalized data bank for a vertical…”
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Journal Article Conference Proceeding -
5
A phenomenological CHF model for mixing-vane spacers in a subchannel of a rod bundle
Published in Annals of nuclear energy (01-07-2020)“…•A phenomenological CHF model for mixing-vane spacers is proposed.•The new model can accurately reflect the influence of spacers on CHF prediction.•Based on…”
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6
Experimental investigation of heat transfer for supercritical pressure water flowing in vertical annular channels
Published in Nuclear engineering and design (01-09-2011)“…► Two annular test sections were constructed with annular gaps of 4 and 6 mm. ► Two heat transfer regions have been observed: normal and deteriorated heat…”
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Overview of methods to increase dryout power in CANDU fuel bundles
Published in Nuclear engineering and design (01-06-2015)“…•Small changes in bundle geometry can have noticeable effects on the bundle CHF.•Rod spacing devices can results in increases of over 200% in CHF.•CHF…”
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8
Measurements of critical heat flux in CANDU 37-element bundle with a steep variation in radial power profile
Published in Nuclear engineering and design (01-02-2010)“…An experiment has been performed to obtain dryout power measurements with a 37-element bundle string simulating radial power profiles of high-enriched fuel…”
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Journal Article Conference Proceeding -
9
A look-up table for fully developed film-boiling heat transfer
Published in Nuclear engineering and design (01-10-2003)“…An improved look-up table for film-boiling heat-transfer coefficients has been derived for steam–water flow inside vertical tubes. Compared to earlier versions…”
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10
An experimental and analytical study of the effect of axial power profile on CHF
Published in Nuclear engineering and design (01-07-2006)“…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…”
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11
Pressure drops for steam and water flow in heated tubes
Published in Nuclear engineering and design (01-01-2005)“…Measurements of pressure drop for a steam and water flow inside several heated tubes were obtained at two different laboratories (Chalk River Laboratories and…”
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12
Thermalhydraulics studies examining the feasibility for introducing slightly enriched uranium fuel into the Embalse CANDU reactor
Published in Nuclear engineering and design (01-09-2007)“…A joint study on the technical feasibility of using 0.9% slightly enriched uranium (SEU) fuel in the Embalse CANDU reactor was performed by Atomic Energy of…”
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Journal Article Conference Proceeding -
13
Prediction of the obstacle effect on film-boiling heat transfer
Published in Nuclear engineering and design (01-03-2005)“…A correlation has been developed to account for the effect of obstacles (simulating the spacing devices in bundles) on heat transfer in dispersed-flow film…”
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14
Comparison of CHF measurements in horizontal and vertical tubes cooled with R-134a
Published in International journal of heat and mass transfer (01-10-2002)“…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…”
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