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Characterization of Sodium Thermal H...
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Weathered, Matthew Thomas.
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Characterization of Sodium Thermal Hydraulics with Optical Fiber Temperature Sensors.
紀錄類型:
書目-電子資源 : Monograph/item
正題名/作者:
Characterization of Sodium Thermal Hydraulics with Optical Fiber Temperature Sensors./
作者:
Weathered, Matthew Thomas.
出版者:
Ann Arbor : ProQuest Dissertations & Theses, : 2017,
面頁冊數:
295 p.
附註:
Source: Dissertation Abstracts International, Volume: 79-04(E), Section: B.
Contained By:
Dissertation Abstracts International79-04B(E).
標題:
Nuclear engineering. -
電子資源:
http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=10690190
ISBN:
9780355549799
Characterization of Sodium Thermal Hydraulics with Optical Fiber Temperature Sensors.
Weathered, Matthew Thomas.
Characterization of Sodium Thermal Hydraulics with Optical Fiber Temperature Sensors.
- Ann Arbor : ProQuest Dissertations & Theses, 2017 - 295 p.
Source: Dissertation Abstracts International, Volume: 79-04(E), Section: B.
Thesis (Ph.D.)--The University of Wisconsin - Madison, 2017.
The thermal hydraulic properties of liquid sodium make it an attractive coolant for use in Generation IV reactors. The liquid metal's high thermal conductivity and low Prandtl number increases efficiency in heat transfer at fuel rods and heat exchangers, but can also cause features such as high magnitude temperature oscillations and gradients in the coolant. Currently, there exists a knowledge gap in the mechanisms which may create these features and their effect on mechanical structures in a sodium fast reactor. Two of these mechanisms include thermal striping and thermal stratification.
ISBN: 9780355549799Subjects--Topical Terms:
595435
Nuclear engineering.
Characterization of Sodium Thermal Hydraulics with Optical Fiber Temperature Sensors.
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The thermal hydraulic properties of liquid sodium make it an attractive coolant for use in Generation IV reactors. The liquid metal's high thermal conductivity and low Prandtl number increases efficiency in heat transfer at fuel rods and heat exchangers, but can also cause features such as high magnitude temperature oscillations and gradients in the coolant. Currently, there exists a knowledge gap in the mechanisms which may create these features and their effect on mechanical structures in a sodium fast reactor. Two of these mechanisms include thermal striping and thermal stratification.
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Thermal striping is the oscillating temperature field created by the turbulent mixing of non-isothermal flows. Usually this occurs at the reactor core outlet or in piping junctions and can cause thermal fatigue in mechanical structures. Meanwhile, thermal stratification results from large volumes of non-isothermal sodium in a pool type reactor, usually caused by a loss of coolant flow accident. This stratification creates buoyancy driven flow transients and high temperature gradients which can also lead to thermal fatigue in reactor structures.
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In order to study these phenomena in sodium, a novel method for the deployment of optical fiber temperature sensors was developed. This method promotes rapid thermal response time and high spatial temperature resolution in the fluid. The thermal striping and stratification behavior in sodium may be experimentally analyzed with these sensors with greater fidelity than ever before.
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Thermal striping behavior at a junction of non-isothermal sodium was fully characterized with optical fibers. An experimental vessel was hydrodynamically scaled to model thermal stratification in a prototypical sodium reactor pool. Novel auxiliary applications of the optical fiber temperature sensors were developed throughout the course of this work. One such application includes local convection coefficient determination in a vessel with the corollary application of level sensing. Other applications were cross correlation velocimetry to determine bulk sodium flow rate and the characterization of coherent vortical structures in sodium with temperature frequency data.
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The data harvested, instrumentation developed and techniques refined in this work will help in the design of more robust reactors as well as validate computational models for licensing sodium fast reactors.
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