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Barclay G. Jones

Affiliations: 
University of Illinois, Urbana-Champaign, Urbana-Champaign, IL 
Area:
Nuclear Engineering
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"Barclay Jones"
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Parents

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Children

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Wen Wu grad student 2007 UIUC
Hitesh Bindra grad student 2010 UIUC
Ling Zou grad student 2010 UIUC
Hyun J. Joe grad student 2011 UIUC

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Publications

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Joe JH, Kim SJ, Jones BG. (2016) A study of solute transport of radiolysis products in crud and its effects on crud growth on PWR fuel pin Nuclear Engineering and Design. 300: 433-451
Kim SJ, Zou L, Jones BG. (2015) An experimental study on sub-cooled flow boiling CHF of R134a at low pressure condition with atmospheric pressure (AP) plasma assisted surface modification International Journal of Heat and Mass Transfer. 81: 362-372
Yao CW, Alvarado JL, Marsh CP, et al. (2014) Wetting behavior on hybrid surfaces with hydrophobic and hydrophilic properties Applied Surface Science. 290: 59-65
Zou L, Jones BG. (2013) Heating surface material’s effect on subcooled flow boiling heat transfer of R134a International Journal of Heat and Mass Transfer. 58: 168-174
Yao CW, Garvin TP, Alvarado JL, et al. (2012) Droplet contact angle behavior on a hybrid surface with hydrophobic and hydrophilic properties Applied Physics Letters. 101
Zou L, Jones BG. (2012) Thermal interaction effect on nucleation site distribution in subcooled boiling International Journal of Heat and Mass Transfer. 55: 2822-2828
Bindra H, Jones BG. (2012) Deposition of metallic colloids under sub-cooled nucleate boiling Colloids and Surfaces a: Physicochemical and Engineering Aspects. 397: 85-91
Wu W, Jones BG, Newell TA. (2009) A statistical model of bubble coalescence and its application to boiling heat flux prediction-Part II: Experimental validation Journal of Heat Transfer. 131
Wu W, Jones BG, Newell TA. (2009) A statistical model of bubble coalescence and its application to boiling heat flux prediction-Part I: Model development Journal of Heat Transfer. 131: 1-11
Chen P, Wu W, Jones BG. (2009) Investigation of surface microgeometry and the active nucleation cavities using AFM Nuclear Engineering and Design. 239: 2035-2041
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