Simulation of QUENCH-15 and QUENCH-19 tests using MELCOR 2.2 code 

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F25%3AN0000094" target="_blank" >RIV/26722445:_____/25:N0000094 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21340/25:00385360

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S002954932500528X" target="_blank" >https://www.sciencedirect.com/science/article/pii/S002954932500528X</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.nucengdes.2025.114351" target="_blank" >10.1016/j.nucengdes.2025.114351</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Simulation of QUENCH-15 and QUENCH-19 tests using MELCOR 2.2 code 

Popis výsledku v původním jazyce

This study presents a benchmarking analysis of the behavior of traditional Zr-based alloy (ZIRLOTM) and accident tolerant fuel cladding candidate FeCrAl based on the QUENCH-15 and QUENCH-19 bundle tests, which simulate severe accident conditions. A sensitivity analysis is conducted on parameters influencing oxidation equations for the tested nuclear fuel materials. A comparative analysis of the simulations performed in three MELCOR 2.2 versions is presented, highlighting differences in hydrogen generation and release and maximum temperature predictions. The results demonstrate that the generic oxidation model is more sensitive to user effect compared to the Arrhenius model for Zr-based alloys. The generic oxidation model sensitivity coefficients do not significantly alter predicted hydrogen production results. Furthermore, it was found that the sensitivity of the results to radiation factors, material used, parameters of the oxidation equations, and other conditions can be utilized in future benchmarking analyses and in modeling for commercial nuclear power plants.

Název v anglickém jazyce

Simulation of QUENCH-15 and QUENCH-19 tests using MELCOR 2.2 code 

Popis výsledku anglicky

This study presents a benchmarking analysis of the behavior of traditional Zr-based alloy (ZIRLOTM) and accident tolerant fuel cladding candidate FeCrAl based on the QUENCH-15 and QUENCH-19 bundle tests, which simulate severe accident conditions. A sensitivity analysis is conducted on parameters influencing oxidation equations for the tested nuclear fuel materials. A comparative analysis of the simulations performed in three MELCOR 2.2 versions is presented, highlighting differences in hydrogen generation and release and maximum temperature predictions. The results demonstrate that the generic oxidation model is more sensitive to user effect compared to the Arrhenius model for Zr-based alloys. The generic oxidation model sensitivity coefficients do not significantly alter predicted hydrogen production results. Furthermore, it was found that the sensitivity of the results to radiation factors, material used, parameters of the oxidation equations, and other conditions can be utilized in future benchmarking analyses and in modeling for commercial nuclear power plants.

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

N - Vyzkumna aktivita podporovana z neverejnych zdroju

Rok uplatnění

2025

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

444

Číslo periodika v rámci svazku

December

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

19

Strana od-do

1-19

Kód UT WoS článku

001544393900002

EID výsledku v databázi Scopus

2-s2.0-105012124061