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dc.contributor.authorGhosh, Sandip
dc.contributor.authorSaha, Samir Kumar
dc.date.accessioned2022-02-05T21:54:26Z
dc.date.available2022-02-05T21:54:26Z
dc.date.copyright3/16/2021 12:00:00 AM
dc.date.issued2021
dc.identifier.issn2332-8983
dc.identifier.otherners_007_03_034503.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4276551
dc.description.abstractThis work demonstrates the leak flow behavior of subcooled water at high pressure and high temperature through a narrow slit analogous to a pipe crack. The modeling and simulations are based on the loss of coolant accident in the primary loop piping of pressurized heavy water reactors where a subcooled liquid is subjected to a rapid depressurization. Prediction of critical leak flow pattern is crucial in the design methodology of costly high energy pipelines in the perspective of leak before break consideration. For a variety of entry and exit conditions, the interphase mass transfer has been studied using computational techniques. Presence of thermodynamic nonequilibrium was detected on several occasions due to high transit velocities. A comparison with experimental findings indicates the validity of a flashing model for safety analysis of similar high energy thermal systems.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleModeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage
dc.typeJournal Paper
dc.journal.volume7
dc.journal.issue3
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4048477
dc.journal.fristpage034503-1
dc.journal.lastpage034503-8
dc.page8
dc.treeJournal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 003
dc.contenttypeFulltext


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