Experimental Method for Measurement of Density and Viscosity of High Temperature Heat Transfer Fluid

Jiaqi Chen, C. S. Brooks

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

In Gen-IV nuclear reactors, various heat transfer fluids are being considered for high temperature application, including molten salts and liquid metals. The thermal physical properties of these heat transfer fluids have relatively large uncertainties when multiple data sources are compared. These uncertainties could come from impurities in the sample, unaccounted systematic error, instrumentation limitations, etc. In this study, the density measurement technique based on Archimedes principle is used. The buoyancy force is measured using a force sensor. The submerged volume is varied using a precision linear stage to accommodate unknown surface tension force of the sample. Verification is made with multiple pure substances at room temperature, and liquid bismuth at elevated temperature. Density of FLiNaK is measured and reported. Moreover, the viscosity measurement technique based on oscillating cup is explored. The conventional rotation measurement is simplified using image processing technique. The sample container and rotary assembly is also simplified using high temperature sealant and customized furnace. Calibration is made with multiple pure substances at room temperature, and a verification study is performed at elevated temperature with bismuth. The potential error sources are discussed as well as possible improvements to the techniques.

Original languageEnglish (US)
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages1437-1450
Number of pages14
ISBN (Electronic)9780894487934
DOIs
StatePublished - 2023
Externally publishedYes
Event20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 - Washington, United States
Duration: Aug 20 2023Aug 25 2023

Publication series

NameProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

Conference

Conference20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Country/TerritoryUnited States
CityWashington
Period8/20/238/25/23

Keywords

  • Archimedes Principle
  • Density
  • FLiNaK
  • Oscillating Cup
  • Viscosity

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Instrumentation

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