Assessing the Phebus FPT-1 experiment: Insights from MELCOR 2.2 and ASYST codes
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F00216305%3A26220%2F24%3APU151840" target="_blank" >RIV/00216305:26220/24:PU151840 - isvavai.cz</a>
Result on the web
<a href="https://www.sciencedirect.com/science/article/pii/S173857332400336X" target="_blank" >https://www.sciencedirect.com/science/article/pii/S173857332400336X</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.net.2024.07.021" target="_blank" >10.1016/j.net.2024.07.021</a>
Alternative languages
Result language
angličtina
Original language name
Assessing the Phebus FPT-1 experiment: Insights from MELCOR 2.2 and ASYST codes
Original language description
Phebus is an experimental facility that represents a scaled-down version of the French 900 MWe pressurized water reactor (PWR) with a ratio of 1/5000. In order to study phenomena occurring during severe accidents in light water reactors, five experiments (FPT-0 to FPT-4) were performed under different fuel and cooling conditions. This paper provides a comprehensive description of the Phebus FPT-1 experiment, MELCOR and ASYST computer codes, discusses the modelling approaches employed and compares the calculated results with the experimental data. To quantitatively assess the results, the Figure of Merits of selected parameters were calculated for both computer codes using ACAP software.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
<a href="/en/project/TM02000039" target="_blank" >TM02000039: Research of coping and mitigation capabilities and strategies of existing and advanced PWRs against Design Extension Conditions</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2024
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Nuclear Engineering and Technology
ISSN
2234-358X
e-ISSN
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Volume of the periodical
56
Issue of the periodical within the volume
12
Country of publishing house
KR - KOREA, REPUBLIC OF
Number of pages
9
Pages from-to
5136-5144
UT code for WoS article
001359557400001
EID of the result in the Scopus database
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