Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code - SI 

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F22%3AN0000038" target="_blank" >RIV/26722445:_____/22:N0000038 - isvavai.cz</a>

Výsledek na webu

<a href="https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/8/3/031201/1086003/Hydrogen-Deflagration-Analysis-in-THAI-Experiments" target="_blank" >https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/8/3/031201/1086003/Hydrogen-Deflagration-Analysis-in-THAI-Experiments</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1115/1.4048006" target="_blank" >10.1115/1.4048006</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code - SI 

Popis výsledku v původním jazyce

The Research Center Rez (CVR) is developing a methodology to simulate nuclear power plants under accidental conditions. A particular effort is focused in the severe accident phenomenology where hydrogen deflagration carries a critical issue for the containment integrity, such as Fukushima Daiichi accident. For this purpose, the Thermal-hydraulics, hydrogen, aerosol and iodine (THAI) experimental campaigns are chosen due to the several tests involved in different conditions. THAI containment test facility is used to open questions concerning the behavior of hydrogen, iodine, and aerosols in the containment of water-cooled reactors during severe accidents.The Fukushima Daiichi Accident demonstrates that the hydrogen deflagration could lead to a significant containment damage. For this reason, a particular attention is given to the hydrogen deflagration scenario. All simulations are prepared and modeled in melcor 2.1. The results obtained showed a strong influence related to some factors such as: the nodalization pattern, control volumes (CVs) number, flow paths (FPs) number, and time-step. In order to assess the THAI model with the THAI final reports, a sensitivity analysis focused on those parameters was performed, which developed four different models with different nodalization.

Název v anglickém jazyce

Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code - SI 

Popis výsledku anglicky

The Research Center Rez (CVR) is developing a methodology to simulate nuclear power plants under accidental conditions. A particular effort is focused in the severe accident phenomenology where hydrogen deflagration carries a critical issue for the containment integrity, such as Fukushima Daiichi accident. For this purpose, the Thermal-hydraulics, hydrogen, aerosol and iodine (THAI) experimental campaigns are chosen due to the several tests involved in different conditions. THAI containment test facility is used to open questions concerning the behavior of hydrogen, iodine, and aerosols in the containment of water-cooled reactors during severe accidents.The Fukushima Daiichi Accident demonstrates that the hydrogen deflagration could lead to a significant containment damage. For this reason, a particular attention is given to the hydrogen deflagration scenario. All simulations are prepared and modeled in melcor 2.1. The results obtained showed a strong influence related to some factors such as: the nodalization pattern, control volumes (CVs) number, flow paths (FPs) number, and time-step. In order to assess the THAI model with the THAI final reports, a sensitivity analysis focused on those parameters was performed, which developed four different models with different nodalization.

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/VI20172020076" target="_blank" >VI20172020076: Zpřesnění predikce radiačních následků těžkých havárií jaderných elektráren s cílem identifikace jejich rizik</a><br>

Návaznosti

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

Rok uplatnění

2022

Kód důvěrnosti údajů

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

Název periodika

Journal of nuclear engineering and radiation science

ISSN

2332-8983

e-ISSN

2332-8975

Svazek periodika

8

Číslo periodika v rámci svazku

3

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

8

Strana od-do

1-8

Kód UT WoS článku

000807102500023

EID výsledku v databázi Scopus

2-s2.0-85133855098