Mesh Sensitivity Analysis of the CFD Model of the Core Catcher of the ALLEGRO Reactor

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F23%3A00374647" target="_blank" >RIV/68407700:21220/23:00374647 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.13182/NURETH20-40672" target="_blank" >http://dx.doi.org/10.13182/NURETH20-40672</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.13182/NURETH20-40672" target="_blank" >10.13182/NURETH20-40672</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Mesh Sensitivity Analysis of the CFD Model of the Core Catcher of the ALLEGRO Reactor

Popis výsledku v původním jazyce

During a severe accident, fuel elements are disrupted, and radionuclides are released. Such a scenario can lead to severe damage to the environment and therefore it is important, that new nuclear projects and designs incorporate strong measures for prevention of severe accidents and mitigation of consequences in case that a severe accident occurs despite the prevention measures. One option for severe accident mitigation, that ensures that the molten core material is cooled down, resolidified and kept in a coolable and safe state is a core catcher. This work focuses on the initial stages of design of a core catcher for gas-cooled fast reactors (GFR), presenting one of the preconceptual design analyses aimed at flow of corium in the core catcher and its heat transfer properties to the walls of the core catcher structure, investigated using CFD software ANSYS Fluent. Numerical simulation investigates transient two-phase flow (corium-N2) in the first phases of corium spreading on core catcher floor, using a Multiphase VOF model. The primary goal of this work is to provide mesh sensitivity analysis and explore the impact of various heat transfer models and material properties libraries. Summary of further CFD analyses to be done during the conceptual design phase is provided as well.

Název v anglickém jazyce

Mesh Sensitivity Analysis of the CFD Model of the Core Catcher of the ALLEGRO Reactor

Popis výsledku anglicky

During a severe accident, fuel elements are disrupted, and radionuclides are released. Such a scenario can lead to severe damage to the environment and therefore it is important, that new nuclear projects and designs incorporate strong measures for prevention of severe accidents and mitigation of consequences in case that a severe accident occurs despite the prevention measures. One option for severe accident mitigation, that ensures that the molten core material is cooled down, resolidified and kept in a coolable and safe state is a core catcher. This work focuses on the initial stages of design of a core catcher for gas-cooled fast reactors (GFR), presenting one of the preconceptual design analyses aimed at flow of corium in the core catcher and its heat transfer properties to the walls of the core catcher structure, investigated using CFD software ANSYS Fluent. Numerical simulation investigates transient two-phase flow (corium-N2) in the first phases of corium spreading on core catcher floor, using a Multiphase VOF model. The primary goal of this work is to provide mesh sensitivity analysis and explore the impact of various heat transfer models and material properties libraries. Summary of further CFD analyses to be done during the conceptual design phase is provided as well.

Druh

D - Stať ve sborníku

CEP obor

—

OECD FORD obor

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

Projekt

<a href="/cs/project/TK01030116" target="_blank" >TK01030116: Návrh konceptu bezpečnostně důležitých prvků rychlého heliem chlazeného demonstračního reaktoru ALLEGRO</a><br>

Návaznosti

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

Rok uplatnění

2023

Kód důvěrnosti údajů

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

Název statě ve sborníku

Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

ISBN

978-0-89448-793-4

ISSN

—

e-ISSN

—

Počet stran výsledku

14

Strana od-do

3956-3969

Název nakladatele

American Nuclear Society, Inc.

Místo vydání

Illinois

Místo konání akce

Washington DC

Datum konání akce

20. 8. 2023

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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