Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment
To ensure the applicability of accident-tolerant fuels, their behaviors under various accidental conditions must be assessed. While the dependences of the behavior of single physical parameters can be investigated in single- or separate-effect experiments, and more complex phenomena can be investiga...
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| Format: | Article |
| Language: | English |
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MDPI AG
2023-03-01
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| Series: | Energies |
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| Online Access: | https://www.mdpi.com/1996-1073/16/6/2763 |
| _version_ | 1827750056859533312 |
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| author | Tereza Abrman Marková Guglielmo Lomonaco Guido Mazzini Martin Ševeček |
| author_facet | Tereza Abrman Marková Guglielmo Lomonaco Guido Mazzini Martin Ševeček |
| author_sort | Tereza Abrman Marková |
| collection | DOAJ |
| description | To ensure the applicability of accident-tolerant fuels, their behaviors under various accidental conditions must be assessed. While the dependences of the behavior of single physical parameters can be investigated in single- or separate-effect experiments, and more complex phenomena can be investigated using integral-effect tests, the behavior of an entire system as complex as a nuclear power plant core must be investigated using computer code modeling. One of the most commonly used computer codes for the assessment of severe accidents is MELCOR 2.2. In version 18019, the authors enabled the modeling of the behavior of the nuclear fuel with FeCrAl cladding (namely, alloy B136Y3) for the first time, using the GOX model. The ability of this model to reasonably accurately predict the behavior of FeCrAl cladding in accident conditions with quenching was verified in this work by modeling the QUENCH-19 experiment carried out in the Karlsruhe Institute of Technology on the QUENCH experimental device and by subsequent comparison of the MELCOR calculation results with the experiment. This article proves that the GOX model can be used to evaluate the behavior of FeCrAl cladding and that the results can be considered conservative. |
| first_indexed | 2024-03-11T06:37:12Z |
| format | Article |
| id | doaj.art-ba54f2d14fe948ae9780139d34bb492f |
| institution | Directory Open Access Journal |
| issn | 1996-1073 |
| language | English |
| last_indexed | 2024-03-11T06:37:12Z |
| publishDate | 2023-03-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Energies |
| spelling | doaj.art-ba54f2d14fe948ae9780139d34bb492f2023-11-17T10:50:38ZengMDPI AGEnergies1996-10732023-03-01166276310.3390/en16062763Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 ExperimentTereza Abrman Marková0Guglielmo Lomonaco1Guido Mazzini2Martin Ševeček3Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, 115 19 Prague, Czech RepublicGeNERG TEC Division, DIME-Dipartimento di Ingegneria Meccanica, Energetica, Gestionale e dei Trasporti, Università Degli Studi di Genova, Via All’Opera Pia 15/A, 16145 Genoa, ItalyDepartment of Nuclear Safety Analyses, National Radiation Protection Institute (SURO), 140 00 Prague, Czech RepublicFaculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, 115 19 Prague, Czech RepublicTo ensure the applicability of accident-tolerant fuels, their behaviors under various accidental conditions must be assessed. While the dependences of the behavior of single physical parameters can be investigated in single- or separate-effect experiments, and more complex phenomena can be investigated using integral-effect tests, the behavior of an entire system as complex as a nuclear power plant core must be investigated using computer code modeling. One of the most commonly used computer codes for the assessment of severe accidents is MELCOR 2.2. In version 18019, the authors enabled the modeling of the behavior of the nuclear fuel with FeCrAl cladding (namely, alloy B136Y3) for the first time, using the GOX model. The ability of this model to reasonably accurately predict the behavior of FeCrAl cladding in accident conditions with quenching was verified in this work by modeling the QUENCH-19 experiment carried out in the Karlsruhe Institute of Technology on the QUENCH experimental device and by subsequent comparison of the MELCOR calculation results with the experiment. This article proves that the GOX model can be used to evaluate the behavior of FeCrAl cladding and that the results can be considered conservative.https://www.mdpi.com/1996-1073/16/6/2763accident-tolerant fuelsMELCORQUENCH 19FeCrAl |
| spellingShingle | Tereza Abrman Marková Guglielmo Lomonaco Guido Mazzini Martin Ševeček Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment Energies accident-tolerant fuels MELCOR QUENCH 19 FeCrAl |
| title | Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment |
| title_full | Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment |
| title_fullStr | Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment |
| title_full_unstemmed | Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment |
| title_short | Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment |
| title_sort | assessment of accident tolerant fuel with fecral cladding behavior using melcor 2 2 based on the results of the quench 19 experiment |
| topic | accident-tolerant fuels MELCOR QUENCH 19 FeCrAl |
| url | https://www.mdpi.com/1996-1073/16/6/2763 |
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