CFD modeling and sensitivity analysis of ex-vessel core melt process

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F19%3A00334866" target="_blank" >RIV/68407700:21220/19:00334866 - isvavai.cz</a>

Výsledek na webu

—

DOI - Digital Object Identifier

—

Jazyk výsledku

angličtina

Název v původním jazyce

CFD modeling and sensitivity analysis of ex-vessel core melt process

Popis výsledku v původním jazyce

The flow and heat transfer behavior of the ex-vessel core melt were investigated using a CFD code ANSYS Fluent along with the experimental data on the spreading of corium available in the literature (VULCANO VE-U7 test). In the numerical simulation of unsteady two-phase flow, the Eulerian Multi-Fluid VOF model was applied for spreading and interfacial surface formation of corium with the surrounding air. The main goal of this work was to provide mesh sensitivity analysis and to explore the impact of the additional heat sink levels towards the concrete substrate on the length of the corium spread. Results show the numerical stability and physical relevancy even for very coarse mesh, which allows for full-scale calculations covering the whole reactor cavity geometry. On the other hand, the effect of the heat flux magnitude transferred to the substrate has relatively low influence.

Název v anglickém jazyce

CFD modeling and sensitivity analysis of ex-vessel core melt process

Popis výsledku anglicky

The flow and heat transfer behavior of the ex-vessel core melt were investigated using a CFD code ANSYS Fluent along with the experimental data on the spreading of corium available in the literature (VULCANO VE-U7 test). In the numerical simulation of unsteady two-phase flow, the Eulerian Multi-Fluid VOF model was applied for spreading and interfacial surface formation of corium with the surrounding air. The main goal of this work was to provide mesh sensitivity analysis and to explore the impact of the additional heat sink levels towards the concrete substrate on the length of the corium spread. Results show the numerical stability and physical relevancy even for very coarse mesh, which allows for full-scale calculations covering the whole reactor cavity geometry. On the other hand, the effect of the heat flux magnitude transferred to the substrate has relatively low influence.

Druh

D - Stať ve sborníku

CEP obor

—

OECD FORD obor

20303 - Thermodynamics

Projekt

<a href="/cs/project/TH02020666" target="_blank" >TH02020666: Pokročilé analytické nástroje pro těžké havárie</a><br>

Návaznosti

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

Rok uplatnění

2019

Kód důvěrnosti údajů

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

Název statě ve sborníku

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019)

ISBN

978-0-89448-767-5

ISSN

—

e-ISSN

—

Počet stran výsledku

12

Strana od-do

2640-2651

Název nakladatele

American Nuclear Society

Místo vydání

New York

Místo konání akce

Portland, Oregon

Datum konání akce

18. 8. 2019

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

—