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dc.contributor.authorCheng, X.
dc.contributor.authorLiu, X. J.
dc.date.accessioned2019-02-28T11:05:21Z
dc.date.available2019-02-28T11:05:21Z
dc.date.copyright12/4/2017 12:00:00 AM
dc.date.issued2018
dc.identifier.issn2332-8983
dc.identifier.otherners_004_01_011003.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252551
dc.description.abstractSupercritical fluids (SCFs) become more and more important in various engineering applications. In nuclear power systems, SCFs are considered as coolant of the reactor core such as the supercritical water-cooled reactor (SCWR), superconducting magnets and blankets in the fusion reactors, or as fluid in the energy conversion systems of the next generation nuclear reactors. Accurate determination of heat transfer and the temperature of the structural material (e.g., fuel rod cladding) is of crucial importance for the system design. Thus, extensive studies on heat transfer to SCFs have been carried out in the past five decades and are still ongoing worldwide. However, no breakthrough is recognized or expected in the near future. In this paper, the status, main challenges, and future R&D needs are briefly reviewed. Three aspects are taken into consideration, i.e., experimental studies, numerical analysis, and model development for the prediction of heat transfer coefficient (HTC). Several key challenges and also the important subjects of the future R&D needs are identified. They are (a) data base for turbulence quantities, (b) multisolution of wall temperature, (c) extensive Reynolds-averaged Navier–Stokes (ERANS) method, and (d) new prediction method for HTC.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleResearch Challenges of Heat Transfer to Supercritical Fluids
dc.typeJournal Paper
dc.journal.volume4
dc.journal.issue1
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4037117
dc.journal.fristpage11003
dc.journal.lastpage011003-7
dc.treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001
dc.contenttypeFulltext


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