Depletion uncertainty analysis to the MYRRHA fuel assembly model
In this work, the objective is to perform an uncertainty analysis on a MYRRHA -Rev.1.6 irradiation cycle study, being applied to a depletion scenario of a single fresh fuel assembly while assuming reflective boundary conditions. Such analysis is statistically based on the application of Wilk’s metho...
| Main Authors: | , , , |
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| Format: | Article |
| Language: | English |
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EDP Sciences
2020-01-01
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| Series: | EPJ Web of Conferences |
| Online Access: | https://www.epj-conferences.org/articles/epjconf/pdf/2020/15/epjconf_nd2019_12001.pdf |
| _version_ | 1831542100229881856 |
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| author | Hernandez Solis Augusto Stankovskiy Alexey Fiorito Luca Van den Eynde Gert |
| author_facet | Hernandez Solis Augusto Stankovskiy Alexey Fiorito Luca Van den Eynde Gert |
| author_sort | Hernandez Solis Augusto |
| collection | DOAJ |
| description | In this work, the objective is to perform an uncertainty analysis on a MYRRHA -Rev.1.6 irradiation cycle study, being applied to a depletion scenario of a single fresh fuel assembly while assuming reflective boundary conditions. Such analysis is statistically based on the application of Wilk’s method of building tolerance limits after 100 depletion calculations were performed with the SERPENT2 code. Due to the computational burden of such type of simulations, this propagation of nuclear data covariances study (allowed by the fast computational performance of SERPENT2) was done at constant power, constant flux and, in a final exercise, at constant power with the addition of fission yield uncertainties (all of these cases employed ENDF/B-VII.1 data). It was observed that while depleting at constant power, the statistical variation of key fission products such as 148Nd is almost not present because of the normalization factor applied to the flux. In contrast, the irradiation at constant flux reveals dependence on burnup. Finally, the added fission yield uncertainties make clear the fact that they directly impact the degree of final uncertainty computed for fission products exemplified by 148Nd and 135Xe important for burnup estimation and reactor operation, respectively. |
| first_indexed | 2024-12-17T00:29:12Z |
| format | Article |
| id | doaj.art-a58638bb8ded482488fdba7ea0e4981f |
| institution | Directory Open Access Journal |
| issn | 2100-014X |
| language | English |
| last_indexed | 2024-12-17T00:29:12Z |
| publishDate | 2020-01-01 |
| publisher | EDP Sciences |
| record_format | Article |
| series | EPJ Web of Conferences |
| spelling | doaj.art-a58638bb8ded482488fdba7ea0e4981f2022-12-21T22:10:23ZengEDP SciencesEPJ Web of Conferences2100-014X2020-01-012391200110.1051/epjconf/202023912001epjconf_nd2019_12001Depletion uncertainty analysis to the MYRRHA fuel assembly modelHernandez Solis Augusto0Stankovskiy Alexey1Fiorito Luca2Van den Eynde Gert3SCK CEN, Boeretang 200SCK CEN, Boeretang 200SCK CEN, Boeretang 200SCK CEN, Boeretang 200In this work, the objective is to perform an uncertainty analysis on a MYRRHA -Rev.1.6 irradiation cycle study, being applied to a depletion scenario of a single fresh fuel assembly while assuming reflective boundary conditions. Such analysis is statistically based on the application of Wilk’s method of building tolerance limits after 100 depletion calculations were performed with the SERPENT2 code. Due to the computational burden of such type of simulations, this propagation of nuclear data covariances study (allowed by the fast computational performance of SERPENT2) was done at constant power, constant flux and, in a final exercise, at constant power with the addition of fission yield uncertainties (all of these cases employed ENDF/B-VII.1 data). It was observed that while depleting at constant power, the statistical variation of key fission products such as 148Nd is almost not present because of the normalization factor applied to the flux. In contrast, the irradiation at constant flux reveals dependence on burnup. Finally, the added fission yield uncertainties make clear the fact that they directly impact the degree of final uncertainty computed for fission products exemplified by 148Nd and 135Xe important for burnup estimation and reactor operation, respectively.https://www.epj-conferences.org/articles/epjconf/pdf/2020/15/epjconf_nd2019_12001.pdf |
| spellingShingle | Hernandez Solis Augusto Stankovskiy Alexey Fiorito Luca Van den Eynde Gert Depletion uncertainty analysis to the MYRRHA fuel assembly model EPJ Web of Conferences |
| title | Depletion uncertainty analysis to the MYRRHA fuel assembly model |
| title_full | Depletion uncertainty analysis to the MYRRHA fuel assembly model |
| title_fullStr | Depletion uncertainty analysis to the MYRRHA fuel assembly model |
| title_full_unstemmed | Depletion uncertainty analysis to the MYRRHA fuel assembly model |
| title_short | Depletion uncertainty analysis to the MYRRHA fuel assembly model |
| title_sort | depletion uncertainty analysis to the myrrha fuel assembly model |
| url | https://www.epj-conferences.org/articles/epjconf/pdf/2020/15/epjconf_nd2019_12001.pdf |
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