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

Result code in 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>

Result on the web

<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>

Result language

angličtina

Original language name

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

Original language description

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.

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

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OECD FORD branch

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

Project

<a href="/en/project/TK01030116" target="_blank" >TK01030116: Conceptual design of safety-important components of helium-cooled fast demonstration reactor ALLEGRO</a><br>

Continuities

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

Publication year

2023

Confidentiality

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

Article name in the collection

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

ISBN

978-0-89448-793-4

ISSN

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e-ISSN

—

Number of pages

14

Pages from-to

3956-3969

Publisher name

American Nuclear Society, Inc.

Place of publication

Illinois

Event location

Washington DC

Event date

Aug 20, 2023

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

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