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

Kód výsledku v 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>

Výsledek na webu

<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

—

Jazyk výsledku

angličtina

Název v původním jazyce

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

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

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

Popis výsledku anglicky

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.

Druh

D - Stať ve sborníku

CEP obor

—

OECD FORD obor

21100 - Other engineering and technologies

Projekt

—

Návaznosti

S - Specificky vyzkum na vysokych skolach

Rok uplatnění

2022

Kód důvěrnosti údajů

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

Název statě ve sborníku

19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics

ISBN

9789076971261

ISSN

—

e-ISSN

—

Počet stran výsledku

16

Strana od-do

—

Název nakladatele

American Nuclear Society, Inc.

Místo vydání

Illinois

Místo konání akce

Brussel

Datum konání akce

6. 3. 2022

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

—