TY - GEN
T1 - Fiber Optic Flow Meter for High Temperature Corrosive Nuclear Environments
AU - Leoschke, M.
AU - Balbier, C.
AU - Lee, S.
AU - Scurti, F.
N1 - Publisher Copyright:
© 2023 Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. All rights reserved.
PY - 2023
Y1 - 2023
N2 - 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.
AB - 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.
UR - http://www.scopus.com/inward/record.url?scp=85202927240&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85202927240&partnerID=8YFLogxK
U2 - 10.13182/NURETH20-40920
DO - 10.13182/NURETH20-40920
M3 - Conference contribution
AN - SCOPUS:85202927240
T3 - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
SP - 1601
EP - 1610
BT - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PB - American Nuclear Society
T2 - 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Y2 - 20 August 2023 through 25 August 2023
ER -