Modeling of Lateral Flow in CFD for Subchannel Analysis

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F22%3A00376437" target="_blank" >RIV/68407700:21340/22:00376437 - isvavai.cz</a>

Výsledek na webu

<a href="https://doi.org/10.1080/00295450.2022.2053807" target="_blank" >https://doi.org/10.1080/00295450.2022.2053807</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1080/00295450.2022.2053807" target="_blank" >10.1080/00295450.2022.2053807</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Modeling of Lateral Flow in CFD for Subchannel Analysis

Popis výsledku v původním jazyce

This paper is aimed at the application of computational fluid dynamics (CFD) calculations for lateral flow modeling in rod bundles of Russian-type pressurized water reactors with hexagonal fuel rod lattice by subchannel analysis under a constant temperature. The subchannel code SUBCAL and CFD code ANSYS Fluent with the Reynolds stress turbulence model, which is capable of solving the anisotropic flow present in rod bundles, are used. Both methods are compared in terms of calculations in rod bundles. The literature review of available experiments of rod bundles suitable for CFD calculation validation follows. This paper describes the created CFD models on a triangular lattice, which are subsequently validated on selected experimental data in a wide range of Reynolds numbers 2.0. 10(4) <= Re <= 1.8 . 10(5) and geometry (pitch-to-rod diameter ratio) 1.06 <= P/D <= 1.50 together with mesh sensitivity analysis. The main part of this work is to develop a new equation for the lateral flow resistance coefficient for the subchannel code based on CFD calculations. Within these calculations, the turbulent mixing coefficient beta for hydraulically smooth rod bundles, which is related to the geometry, and the momentumenergy transfer analogy correction factor e are also evaluated and for which the equation is subsequently proposed.

Název v anglickém jazyce

Modeling of Lateral Flow in CFD for Subchannel Analysis

Popis výsledku anglicky

This paper is aimed at the application of computational fluid dynamics (CFD) calculations for lateral flow modeling in rod bundles of Russian-type pressurized water reactors with hexagonal fuel rod lattice by subchannel analysis under a constant temperature. The subchannel code SUBCAL and CFD code ANSYS Fluent with the Reynolds stress turbulence model, which is capable of solving the anisotropic flow present in rod bundles, are used. Both methods are compared in terms of calculations in rod bundles. The literature review of available experiments of rod bundles suitable for CFD calculation validation follows. This paper describes the created CFD models on a triangular lattice, which are subsequently validated on selected experimental data in a wide range of Reynolds numbers 2.0. 10(4) <= Re <= 1.8 . 10(5) and geometry (pitch-to-rod diameter ratio) 1.06 <= P/D <= 1.50 together with mesh sensitivity analysis. The main part of this work is to develop a new equation for the lateral flow resistance coefficient for the subchannel code based on CFD calculations. Within these calculations, the turbulent mixing coefficient beta for hydraulically smooth rod bundles, which is related to the geometry, and the momentumenergy transfer analogy correction factor e are also evaluated and for which the equation is subsequently proposed.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10304 - Nuclear physics

Projekt

—

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2022

Kód důvěrnosti údajů

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

Název periodika

Nuclear Technology

ISSN

0029-5450

e-ISSN

1943-7471

Svazek periodika

208

Číslo periodika v rámci svazku

10

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

14

Strana od-do

1591-1604

Kód UT WoS článku

000803997700001

EID výsledku v databázi Scopus

2-s2.0-85131369761