EXPERIMENTAL INVESTIGATION OF CRITICAL HEAT FLUX IN ANNULUS AT LOW PRESSURE AND LOW FLOW PARAMETERS

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F00216305%3A26220%2F20%3APU138457" target="_blank" >RIV/00216305:26220/20:PU138457 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21340/20:00345754

Výsledek na webu

<a href="https://ojs.cvut.cz/ojs/index.php/APP/article/view/6916" target="_blank" >https://ojs.cvut.cz/ojs/index.php/APP/article/view/6916</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.14311/APP.2020.28.0050" target="_blank" >10.14311/APP.2020.28.0050</a>

Jazyk výsledku

angličtina

Název v původním jazyce

EXPERIMENTAL INVESTIGATION OF CRITICAL HEAT FLUX IN ANNULUS AT LOW PRESSURE AND LOW FLOW PARAMETERS

Popis výsledku v původním jazyce

Steady state flow boiling experiments were conducted on a technically smooth Inconel 625 tube with outer diameter 9.1 mm at inlet pressures 131, 220 and 323 kPa, inlet temperatures 62, 78 and 94 °C and approximately 400, 600 and 1000 kg/(m2.s) mass flow. Water of these parameters was entering into the vertically aligned annulus, where the uniformly heated tube was placed until the critical heat flux (CHF) appeared. The experimental data were compared to estimations of CHF by local PGT tube correlation and Groeneveld’s look-up tables for tubes. The results imply that in the region of low pressure and low mass flux, the differences between calculations and experiments are substantial (more than 50 % of CHF). The calculations further imply that look-up tables and tube correlations should be corrected to the annulus geometry. Here, the Doerffer’s approach was chosen and led to a substantial enhancement of CHF estimation. Yet, a new correlation for the region of low pressure and flow is needed.

Název v anglickém jazyce

EXPERIMENTAL INVESTIGATION OF CRITICAL HEAT FLUX IN ANNULUS AT LOW PRESSURE AND LOW FLOW PARAMETERS

Popis výsledku anglicky

Steady state flow boiling experiments were conducted on a technically smooth Inconel 625 tube with outer diameter 9.1 mm at inlet pressures 131, 220 and 323 kPa, inlet temperatures 62, 78 and 94 °C and approximately 400, 600 and 1000 kg/(m2.s) mass flow. Water of these parameters was entering into the vertically aligned annulus, where the uniformly heated tube was placed until the critical heat flux (CHF) appeared. The experimental data were compared to estimations of CHF by local PGT tube correlation and Groeneveld’s look-up tables for tubes. The results imply that in the region of low pressure and low mass flux, the differences between calculations and experiments are substantial (more than 50 % of CHF). The calculations further imply that look-up tables and tube correlations should be corrected to the annulus geometry. Here, the Doerffer’s approach was chosen and led to a substantial enhancement of CHF estimation. Yet, a new correlation for the region of low pressure and flow is needed.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

<a href="/cs/project/LTAUSA18198" target="_blank" >LTAUSA18198: ADAR - Pokročilý jaderný reaktor řízený urychlovačem</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2020

Kód důvěrnosti údajů

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

Název statě ve sborníku

ŠIMÁNĚ 2020: Student Conference on Nuclear Engineering

ISBN

978-80-01-06794-9

ISSN

2336-5382

e-ISSN

—

Počet stran výsledku

9

Strana od-do

50-58

Název nakladatele

Czech Technical University in Prague

Místo vydání

Praha

Místo konání akce

ČVUT v Praze

Datum konání akce

23. 6. 2020

Typ akce podle státní příslušnosti

EUR - Evropská akce

Kód UT WoS článku

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