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dc.contributor.authorYuan, Zhou
dc.contributor.authorYangle, Wang
dc.contributor.authorJingtan, Chen
dc.contributor.authorZhaoyang, Xia
dc.contributor.authorJunfeng, Wang
dc.date.accessioned2019-02-28T11:05:50Z
dc.date.available2019-02-28T11:05:50Z
dc.date.copyright12/4/2017 12:00:00 AM
dc.date.issued2018
dc.identifier.issn2332-8983
dc.identifier.otherners_004_01_011018.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252638
dc.description.abstractThe supercritical carbon dioxide (S-CO2) Brayton gas turbine cycle has been studied as an efficient and cost-effective option for advanced power systems. One major safety issue for any power cycle is a pipe break and the associated discharge of the working fluid and subsequent decrease in system pressure. In this paper, an S-CO2 critical flow in the nozzle tube is analyzed numerically with fluent 15.0. The Redlich–Kwong real gas equation is selected to calculate carbon dioxide density and the standard k-epsilon turbulence model is selected. Experimental data are used as a benchmark to examine the capability of the current approach. Compared with experimental data, the simulation results overestimate the critical mass flux; the error range is between 15% and 25%. The simulation results show that as L/D increases, critical mass flow decreases. As stagnation temperature increases, critical mass flow decreases. The complex thermal hydraulic behavior in the nozzle tubes is analyzed. Three flow patterns in the nozzle tube during transient critical flow are obtained and discussed. From inlet to outlet of the tube, CO2 may undergo the following phases in turn: (1) supercritical phase; (2) supercritical phase—gas phase; (3) supercritical phase—gas phase—liquid phase. The simulation results are also helpful for further experimental and theoretical research.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleNumerical Simulation of Supercritical Carbon Dioxide Critical Flow in the Nozzle Tube
dc.typeJournal Paper
dc.journal.volume4
dc.journal.issue1
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4037896
dc.journal.fristpage11018
dc.journal.lastpage011018-5
dc.treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001
dc.contenttypeFulltext


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