Status of computational fluid dynamics for in-vessel retention: Challenges and achievements

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F20%3AN0000045" target="_blank" >RIV/46356088:_____/20:N0000045 - isvavai.cz</a>

Result on the web

<a href="https://www.sciencedirect.com/science/article/pii/S0306454919305067" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0306454919305067</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.anucene.2019.107004" target="_blank" >10.1016/j.anucene.2019.107004</a>

Result language

angličtina

Original language name

Status of computational fluid dynamics for in-vessel retention: Challenges and achievements

Original language description

During a severe accident in a nuclear reactor, core damage occurs and may lead to the formation of corium, followed by relocation to the vessel lower head. The decay heat released by the corium can threaten the integrity of the vessel, if no effective cooling mechanism is in place. In-Vessel Retention (IVR) is a severe accident mitigation strategy that has been shown to work for low-to-intermediate power reactors. For high power reactors, many uncertainties still exist. In an attempt to remove some of these uncertainties, the European H2020 IVMR project was launched in 2015. The focus of this project is on obtaining the additional, necessary, experimental data in order to improve on current modelling strategies. One of the modelling strategies investigated is the potential use of CFD codes in assessing the feasibility of IVR for high power reactors. The main focus of the CFD studies is on two important aspects of IVR: the presence of a metallic layer on top of the corium pool and the homogenous corium pool. These aspects are analysed by studying the thermal hydraulic features of a thin metal layer and that of a homogeneous pool. In this paper, first the used codes and numerical approaches are presented. The numerical models are subsequently assessed by comparing numerical results with relevant simulant-based experimental data, resulting, in general, in good agreement. The codes are then used to perform exploratory computations under prototypical conditions. While the behaviours of water and prototypical materials are similar for the oxide pool, significant differences are observed for the metallic layer.

Czech name

—

Czech description

—

Type

J_imp - Article in a specialist periodical, which is included in the Web of Science database

CEP classification

—

OECD FORD branch

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

Project

—

Continuities

R - Projekt Ramcoveho programu EK

Publication year

2020

Confidentiality

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

Name of the periodical

Annals of Nuclear Energy

ISSN

0306-4549

e-ISSN

—

Volume of the periodical

135

Issue of the periodical within the volume

January

Country of publishing house

GB - UNITED KINGDOM

Number of pages

12

Pages from-to

1-12

UT code for WoS article

000496898500052

EID of the result in the Scopus database

2-s2.0-85071371544