Assessing the Phebus FPT-1 experiment: Insights from MELCOR 2.2 and ASYST codes
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Mičian, Peter
Černý, Tomáš
Petrosyan, Taron
Foral, Štěpán
Katovský, Karel
Ptáček, Michal
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Mark
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Korean Nuclear Society
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Abstract
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.
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.
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.
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MELCOR , ASYST , Phebus FPT-1 , ACAP , Figure of Merit , Thermal-hydraulics , MELCOR , ASYST , Phebus FPT-1 , ACAP , Figure of Merit , Thermal-hydraulics
Citation
Nuclear Engineering and Technology. 2024, vol. 56, issue 12, p. 5136-5144.
https://www.sciencedirect.com/science/article/pii/S173857332400336X
https://www.sciencedirect.com/science/article/pii/S173857332400336X
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en
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Except where otherwised noted, this item's license is described as Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International

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