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contributor authorBagul, R. K.
contributor authorPilkhwal, D. S.
contributor authorVijayan, P. K.
contributor authorJoshi, J. B.
date accessioned2019-03-17T09:40:56Z
date available2019-03-17T09:40:56Z
date copyright1/24/2019 12:00:00 AM
date issued2019
identifier issn2332-8983
identifier otherners_005_01_011004.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4255612
description abstractAdvanced heavy water reactor (AHWR) is a natural circulation-based, light water-cooled, heavy water-moderated pressure tube type of nuclear reactor. In AHWR, the steam separation takes place in horizontal steam drums purely based on gravity separation principle. It is a known fact that efficiency of gravity separation is affected by the carryover phenomenon, i.e., conveyance of water droplets by the steam. To minimize the carryover, it is advised to reduce the superficial velocities of phases. Lowering the flow velocities also results in to lower pressure drop, which is very much desired. However, careful attention must be given to carryover phenomenon during design. An experimental test facility known as air–water loop (AWL) simulating the scaled down steam drum of AHWR with air–water mixture has been designed and experimental work performed on carryover phenomenon is presented here. Comparison of measured entrainment fraction with existing correlations and other visual observations are described. Numerical simulations with Euler–Lagrangian method have been carried out for which droplet size distribution measured experimentally is used as an input.
publisherThe American Society of Mechanical Engineers (ASME)
titleExperimental Investigations on Carryover in a Gravity Separation-Based Steam Drum
typeJournal Paper
journal volume5
journal issue1
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4041791
journal fristpage11004
journal lastpage011004-12
treeJournal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001
contenttypeFulltext


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