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dc.contributor.authorKorinek, Tomas
dc.contributor.authorSkoda, Radek
dc.contributor.authorLovecky, Martin
dc.contributor.authorBurian, Ondrej
dc.date.accessioned2024-04-24T22:42:50Z
dc.date.available2024-04-24T22:42:50Z
dc.date.copyright10/20/2023 12:00:00 AM
dc.date.issued2023
dc.identifier.issn2332-8983
dc.identifier.otherners_010_01_014501.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4295735
dc.description.abstractThe heavy water reactor concept Teplator is a pressure channel type reactor with independent systems for the primary coolant and the moderator. The present study analyses the low-pressure moderator cooling system of Teplator during full-power operation. The moderator is heated from neutron thermalization, gamma rays absorption, fission product decay, and decay of activation products. Additionally, heat transfer from the coolant channels has to be taken in the analyses of the moderator cooling system. Preliminary thermal-hydraulic analyses of the cooling system are supplemented by computational fluid dynamics (CFD) simulations of heat and fluid flow in the moderator's vessel, emphasizing flow-type regimes. Results from CFD simulations showed that the buoyancy-dominated flow (case MF-22) resulted in a higher thermal stratification and high moderator temperature close to the upper plate of the moderator vessel. The inertia-dominated flow regime MF-90 resulted in good mixing of the moderator and a low thermal stratification in the vessel. Finally, the midmass flow rate regime MF-45 was identified as a transitional region from a buoyancy-dominated to a mix-type regime.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleComputational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor
dc.typeJournal Paper
dc.journal.volume10
dc.journal.issue1
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4063007
dc.journal.fristpage14501-1
dc.journal.lastpage14501-7
dc.page7
dc.treeJournal of Nuclear Engineering and Radiation Science:;2023:;volume( 010 ):;issue: 001
dc.contenttypeFulltext


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