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

Kód výsledku v 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>

Výsledek na webu

<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>

Jazyk výsledku

angličtina

Název v původním jazyce

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

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

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

Popis výsledku anglicky

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.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

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

Projekt

—

Návaznosti

R - Projekt Ramcoveho programu EK

Rok uplatnění

2020

Kód důvěrnosti údajů

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

Název periodika

Annals of Nuclear Energy

ISSN

0306-4549

e-ISSN

—

Svazek periodika

135

Číslo periodika v rámci svazku

January

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

12

Strana od-do

1-12

Kód UT WoS článku

000496898500052

EID výsledku v databázi Scopus

2-s2.0-85071371544