Investigation of Prototypical Corium Interaction with Samples of VVER-1000 In-Vessel and Ex-Vessel Structures

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F24%3AN0000021" target="_blank" >RIV/26722445:_____/24:N0000021 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/00216208:11310/24:10477522 RIV/46356088:_____/24:N0000025

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S0029549323007094" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0029549323007094</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.nucengdes.2023.112860" target="_blank" >10.1016/j.nucengdes.2023.112860</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Investigation of Prototypical Corium Interaction with Samples of VVER-1000 In-Vessel and Ex-Vessel Structures

Popis výsledku v původním jazyce

After the Fukushima Daiichi accident, many countries worldwide conducted stress tests for nuclear power plants (NPPs) in operation. These tests initiated back-fitting activities. One of the long-term back-fitting tasks for VVER-1000 reactors involves managing the ex-vessel phase of a hypothetical severe accident (SA). The challenge is to cool down the corium ejected into the reactor cavity after a reactor pressure vessel (RPV) failure by spreading it onto the dedicated area. However, to transport the corium to this area, the thermal shielding must withstand the load of poured corium. The thermal shielding ability must be investigated to maintain this strategy successfully. Moreover, the internal RPV parts may prolong the time of RPV failure and decrease the temperature of the corium ejected from the failed RPV. This phenomenon needs to be verified experimentally. Therefore, the interaction of simulated corium with the internal RPV parts and thermal shielding samples was studied experimentally. These experimental findings may help to understand the corium behavior and its cooling during severe accidents in VVER-1000 reactors.

Název v anglickém jazyce

Investigation of Prototypical Corium Interaction with Samples of VVER-1000 In-Vessel and Ex-Vessel Structures

Popis výsledku anglicky

After the Fukushima Daiichi accident, many countries worldwide conducted stress tests for nuclear power plants (NPPs) in operation. These tests initiated back-fitting activities. One of the long-term back-fitting tasks for VVER-1000 reactors involves managing the ex-vessel phase of a hypothetical severe accident (SA). The challenge is to cool down the corium ejected into the reactor cavity after a reactor pressure vessel (RPV) failure by spreading it onto the dedicated area. However, to transport the corium to this area, the thermal shielding must withstand the load of poured corium. The thermal shielding ability must be investigated to maintain this strategy successfully. Moreover, the internal RPV parts may prolong the time of RPV failure and decrease the temperature of the corium ejected from the failed RPV. This phenomenon needs to be verified experimentally. Therefore, the interaction of simulated corium with the internal RPV parts and thermal shielding samples was studied experimentally. These experimental findings may help to understand the corium behavior and its cooling during severe accidents in VVER-1000 reactors.

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

<a href="/cs/project/TK03020149" target="_blank" >TK03020149: Měření vlastností koria a analýzy jeho rozlivu při vysokých teplotách</a><br>

Návaznosti

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

Rok uplatnění

2024

Kód důvěrnosti údajů

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

Název periodika

Nuclear Engineering and Design

ISSN

0029-5493

e-ISSN

1872-759X

Svazek periodika

418

Číslo periodika v rámci svazku

March

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

14

Strana od-do

1-14

Kód UT WoS článku

001153109300001

EID výsledku v databázi Scopus

2-s2.0-85181584844