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

Result code in 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>

Alternative codes found

RIV/68407700:21340/25:00385360

Result on the web

<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>

Result language

angličtina

Original language name

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

Original language description

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.

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

N - Vyzkumna aktivita podporovana z neverejnych zdroju

Publication year

2025

Confidentiality

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

Name of the periodical

Nuclear Engineering and Design

ISSN

0029-5493

e-ISSN

1872-759X

Volume of the periodical

444

Issue of the periodical within the volume

December

Country of publishing house

CH - SWITZERLAND

Number of pages

19

Pages from-to

1-19

UT code for WoS article

001544393900002

EID of the result in the Scopus database

2-s2.0-105012124061