Fiber Optic Flow Meter for High Temperature Corrosive Nuclear Environments

M. Leoschke, C. Balbier, S. Lee, F. Scurti

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

1 Scopus citations

Abstract

The process of determining fluid flow rates has applications in a variety of settings. In nuclear applications, such as advanced fission reactors or fusion tokamak blankets, these instruments have the additional requirement of tolerating harsh environmental factors, such as high temperatures, corrosive chemistry, and ionizing radiation. This paper shows results related to development and experimental demonstration of flow measurements using a hot wire based on optical fibers. More specifically, we report on the development of several fiber optic hot-wire designs, including experimental results at various temperatures, validation against conventional techniques, and pros and cons of each conceptual design. Experimental results obtained using this approach show the ability to measure flow rates at fluid temperatures as high a 460 °C, as well as spatially resolve velocity profiles.

Original languageEnglish (US)
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages1601-1610
Number of pages10
ISBN (Electronic)9780894487934
DOIs
StatePublished - 2023
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

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Instrumentation

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