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Measurement of Wall Temperature Fluctuations during Thermal Mixing of Non-isothermal Water Streams
KTH, School of Engineering Sciences (SCI), Physics, Reactor Technology.ORCID iD: 0000-0001-5595-1952
KTH, School of Engineering Sciences (SCI), Physics, Reactor Technology.ORCID iD: 0000-0001-8743-7157
KTH, School of Engineering Sciences (SCI), Physics, Reactor Technology.
KTH, School of Engineering Sciences (SCI), Physics, Particle and Astroparticle Physics.
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2015 (English)In: Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), American Nuclear Society, 2015Conference paper (Refereed)
Abstract [en]

This paper is dealing with measurement of temperature fluctuations during mixing of two water streams in an annular test section at BWR operational conditions. The experiments are simulating conditions existing in a guide tube of BWR control rods, where relatively cold water at about 333 K is mixing with hot water at ~550 K. It is shown that the mixing is causing high amplitude temperature fluctuations in the solid walls of the control rod extender. Using new movable multi-sensors it became possible to obtain a large experimental database, containing wall temperature measurements at 8 azimuthal and 5 axial positions, with 13 thermocouples at each position. In total 520 temperature readings were performed, each lasting about 2 minutes and recording transient temperature with frequency of at least 100 samples per second and with estimated non-calibrated uncertainty less than 3.9 K. The present experimental results can be used to analyze the governing phenomena during thermal mixing and also to validate CFD conjugate heat transfer models of thermal mixing applied to actual reactor geometries.

Place, publisher, year, edition, pages
American Nuclear Society, 2015.
Keyword [en]
Thermal mixing, thermal fatigue, temperature oscillations
National Category
Energy Engineering
Identifiers
URN: urn:nbn:se:kth:diva-186295ScopusID: 2-s2.0-84962764476OAI: oai:DiVA.org:kth-186295DiVA: diva2:926780
Conference
16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015; Chicago; United States
Projects
THEMFE
Funder
Swedish Radiation Safety Authority, 47385
Note

QC 20160512

Available from: 2016-05-09 Created: 2016-05-09 Last updated: 2016-05-12Bibliographically approved

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Anglart, HenrykBergagio, MattiaHedberg, StellanRydström, Stefan
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