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contributor authorBeuthe, Thomas
contributor authorVasić, Aleksandar
contributor authorAzih, Chukwudi
contributor authorMaqueo, Pablo D. G.
date accessioned2024-04-24T22:42:52Z
date available2024-04-24T22:42:52Z
date copyright10/20/2023 12:00:00 AM
date issued2023
identifier issn2332-8983
identifier otherners_010_02_020801.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4295737
description abstractAdvanced small modular reactors strive to improve reactor safety through increased utilization of passive heat transport and safety systems. An innovative means of meeting this design goal is to use alkali metal heat pipes to cool the reactor under both normal and abnormal operating conditions. A heat pipe model has been added to the ARIANT thermalhydraulic code to enable reactor modeling and support the design and licensing of new reactors. Saturation fluid properties are a fundamental input to this model. Consequently, this article provides a comprehensive comparative overview of the best available sodium saturation property correlations developed over the past century. The results show most of the sodium property correlations needed to model a heat pipe are relatively well-defined and recommendations for their use can be provided.
publisherThe American Society of Mechanical Engineers (ASME)
titleDevelopment of Analysis Tools for Heat Pipes Used in Small Modular Reactors: Sodium Property Correlations
typeJournal Paper
journal volume10
journal issue2
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4063112
journal fristpage20801-1
journal lastpage20801-19
page19
treeJournal of Nuclear Engineering and Radiation Science:;2023:;volume( 010 ):;issue: 002
contenttypeFulltext


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