Investigation of surface structure effects on the Flow Boiling Critical Heat Flux values

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F22%3A00366364" target="_blank" >RIV/68407700:21340/22:00366364 - isvavai.cz</a>

Result on the web

<a href="https://www.sckcen.be/en/events-courses/nureth-19-lead-flow" target="_blank" >https://www.sckcen.be/en/events-courses/nureth-19-lead-flow</a>

DOI - Digital Object Identifier

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Result language

angličtina

Original language name

Investigation of surface structure effects on the Flow Boiling Critical Heat Flux values

Original language description

An analysis of flow boiling critical heat flux (CHF) data was performed to implement the contact angle effect using a suitable CHF correlation. A total number of 69 experimental runs were recorded from the steady-state flow boiling experiments with Zirconium alloy cladding material and the previously measured 43 runs with smooth Inconel material were used for comparison. The experiments were performed in a vertical, internally heated, concentric annular test section composed of a glass tube containing a heated tube with an outer diameter of 9.14 mm and a length of 365 mm. The flow parameters were set to low pressure in the range of 120 kPa to 300 kPa and low mass flux in the range of 400 to 800 kg/(m^2.s). Both roughness and static contact angle were measured before the experiments. After several days of CHF experiments, a thin super-hydrophilic layer was apparent on the heated tube surface. Therefore, the experiments were split into two sets of results based on the time spent in the test section. In another work, several empirical correlations were used to predict the CHF in the test section to find the most suitable one. Because any available CHF correlation for flow boiling has not implemented the surface structure effects yet, several corrective factors based on pool boiling experiments were used to enhance the available correlation. With this approach, only limited differences in wettability could be covered. A new corrective factor is also proposed.

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

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OECD FORD branch

21100 - Other engineering and technologies

Project

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Continuities

S - Specificky vyzkum na vysokych skolach

Publication year

2022

Confidentiality

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Article name in the collection

19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics

ISBN

9789076971261

ISSN

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e-ISSN

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Number of pages

16

Pages from-to

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Publisher name

American Nuclear Society, Inc.

Place of publication

Illinois

Event location

Brussel

Event date

Mar 6, 2022

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

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