CFD modeling and sensitivity analysis of ex-vessel core melt process
The result's identifiers
Result code in 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>
Result on the web
—
DOI - Digital Object Identifier
—
Alternative languages
Result language
angličtina
Original language name
CFD modeling and sensitivity analysis of ex-vessel core melt process
Original language description
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.
Czech name
—
Czech description
—
Classification
Type
D - Article in proceedings
CEP classification
—
OECD FORD branch
20303 - Thermodynamics
Result continuities
Project
<a href="/en/project/TH02020666" target="_blank" >TH02020666: Advanced Analytical Tools for Severe Accident Simulations</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2019
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019)
ISBN
978-0-89448-767-5
ISSN
—
e-ISSN
—
Number of pages
12
Pages from-to
2640-2651
Publisher name
American Nuclear Society
Place of publication
New York
Event location
Portland, Oregon
Event date
Aug 18, 2019
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
—