Sensitivity analysis for subcooled flow boiling using Eulerian CFD approach

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F23%3A00363510" target="_blank" >RIV/68407700:21340/23:00363510 - isvavai.cz</a>

Výsledek na webu

<a href="https://doi.org/10.1016/j.nucengdes.2023.112194" target="_blank" >https://doi.org/10.1016/j.nucengdes.2023.112194</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.nucengdes.2023.112194" target="_blank" >10.1016/j.nucengdes.2023.112194</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Sensitivity analysis for subcooled flow boiling using Eulerian CFD approach

Popis výsledku v původním jazyce

This paper presents capability of Eulerian CFD (Computational Fluid Dynamics) approach using sensitivity-analysis-based model to predict subcooled boiling flows in the DEBORA experiment, the conditions corresponding to those in PWRs (Pressurized Water Reactors). The main feature of the developed model is a good estimation of the void fraction distribution in a cross section of a heated pipe, not only in the lower void regime but also in the high void regime (), which is achieved by modifying the lift force coefficients in the model developed by Baglietto’s group. In addition, the Sauter diameter profile is well predicted by employing the MUSIG population balance model, in which the coalescence and breakage factors are tuned to the experiments. A nucleation site density model recently proposed by Li is employed together with the Tolubinsky and Kostanchuk bubble departure diameter model, whose coefficient is again obtained via a sensitivity analysis. The model developed in this work, CTU-PSI model, is expected to be applied to boiling flow simulations in PWRs.

Název v anglickém jazyce

Sensitivity analysis for subcooled flow boiling using Eulerian CFD approach

Popis výsledku anglicky

This paper presents capability of Eulerian CFD (Computational Fluid Dynamics) approach using sensitivity-analysis-based model to predict subcooled boiling flows in the DEBORA experiment, the conditions corresponding to those in PWRs (Pressurized Water Reactors). The main feature of the developed model is a good estimation of the void fraction distribution in a cross section of a heated pipe, not only in the lower void regime but also in the high void regime (), which is achieved by modifying the lift force coefficients in the model developed by Baglietto’s group. In addition, the Sauter diameter profile is well predicted by employing the MUSIG population balance model, in which the coalescence and breakage factors are tuned to the experiments. A nucleation site density model recently proposed by Li is employed together with the Tolubinsky and Kostanchuk bubble departure diameter model, whose coefficient is again obtained via a sensitivity analysis. The model developed in this work, CTU-PSI model, is expected to be applied to boiling flow simulations in PWRs.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10700 - Other natural sciences

Projekt

—

Návaznosti

S - Specificky vyzkum na vysokych skolach

Rok uplatnění

2023

Kód důvěrnosti údajů

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

Název periodika

Nuclear Engineering and Design

ISSN

0029-5493

e-ISSN

1872-759X

Svazek periodika

Volume 405

Číslo periodika v rámci svazku

112194

Stát vydavatele periodika

NL - Nizozemsko

Počet stran výsledku

21

Strana od-do

—

Kód UT WoS článku

000938756700001

EID výsledku v databázi Scopus

2-s2.0-85147607779