A Two-Step Approach to Uncertainty Quantification of Core Simulators
For the multiple sources of error introduced into the standard computational regime for simulating reactor cores, rigorous uncertainty analysis methods are available primarily to quantify the effects of cross section uncertainties. Two methods for propagating cross section uncertainties through core...
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| Format: | Article |
| Language: | English |
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Wiley
2012-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2012/767096 |
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| author | Artem Yankov Benjamin Collins Markus Klein Matthew A. Jessee Winfried Zwermann Kiril Velkov Andreas Pautz Thomas Downar |
| author_facet | Artem Yankov Benjamin Collins Markus Klein Matthew A. Jessee Winfried Zwermann Kiril Velkov Andreas Pautz Thomas Downar |
| author_sort | Artem Yankov |
| collection | DOAJ |
| description | For the multiple sources of error introduced into the standard computational regime for simulating reactor cores, rigorous uncertainty analysis methods are available primarily to quantify the effects of cross section uncertainties. Two methods for propagating cross section uncertainties through core simulators are the XSUSA statistical approach and the “two-step” method. The XSUSA approach, which is based on the SUSA code package, is fundamentally a stochastic sampling method. Alternatively, the two-step method utilizes generalized perturbation theory in the first step and stochastic sampling in the second step. The consistency of these two methods in quantifying uncertainties in the multiplication factor and in the core power distribution was examined in the framework of phase I-3 of the OECD Uncertainty Analysis in Modeling benchmark. With the Three Mile Island Unit 1 core as a base model for analysis, the XSUSA and two-step methods were applied with certain limitations, and the results were compared to those produced by other stochastic sampling-based codes. Based on the uncertainty analysis results, conclusions were drawn as to the method that is currently more viable for computing uncertainties in burnup and transient calculations. |
| format | Article |
| id | doaj-art-6a61eb7ebecc47fa860c2d28109de13a |
| institution | OA Journals |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2012-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-6a61eb7ebecc47fa860c2d28109de13a2025-08-20T02:06:05ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832012-01-01201210.1155/2012/767096767096A Two-Step Approach to Uncertainty Quantification of Core SimulatorsArtem Yankov0Benjamin Collins1Markus Klein2Matthew A. Jessee3Winfried Zwermann4Kiril Velkov5Andreas Pautz6Thomas Downar7Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Boulevard, Ann Arbor, MI 48109, USADepartment of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Boulevard, Ann Arbor, MI 48109, USAReactor Safety Research Division, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Boltzmannstraße 14, 85748 Garching bei München, GermanyReactor and Nuclear Systems Division, Oak Ridge National Laboratory, P.O. Box 2008 MS6172, Oak Ridge, TN 37831, USAReactor Safety Research Division, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Boltzmannstraße 14, 85748 Garching bei München, GermanyReactor Safety Research Division, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Boltzmannstraße 14, 85748 Garching bei München, GermanyReactor Safety Research Division, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Boltzmannstraße 14, 85748 Garching bei München, GermanyDepartment of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Boulevard, Ann Arbor, MI 48109, USAFor the multiple sources of error introduced into the standard computational regime for simulating reactor cores, rigorous uncertainty analysis methods are available primarily to quantify the effects of cross section uncertainties. Two methods for propagating cross section uncertainties through core simulators are the XSUSA statistical approach and the “two-step” method. The XSUSA approach, which is based on the SUSA code package, is fundamentally a stochastic sampling method. Alternatively, the two-step method utilizes generalized perturbation theory in the first step and stochastic sampling in the second step. The consistency of these two methods in quantifying uncertainties in the multiplication factor and in the core power distribution was examined in the framework of phase I-3 of the OECD Uncertainty Analysis in Modeling benchmark. With the Three Mile Island Unit 1 core as a base model for analysis, the XSUSA and two-step methods were applied with certain limitations, and the results were compared to those produced by other stochastic sampling-based codes. Based on the uncertainty analysis results, conclusions were drawn as to the method that is currently more viable for computing uncertainties in burnup and transient calculations.http://dx.doi.org/10.1155/2012/767096 |
| spellingShingle | Artem Yankov Benjamin Collins Markus Klein Matthew A. Jessee Winfried Zwermann Kiril Velkov Andreas Pautz Thomas Downar A Two-Step Approach to Uncertainty Quantification of Core Simulators Science and Technology of Nuclear Installations |
| title | A Two-Step Approach to Uncertainty Quantification of Core Simulators |
| title_full | A Two-Step Approach to Uncertainty Quantification of Core Simulators |
| title_fullStr | A Two-Step Approach to Uncertainty Quantification of Core Simulators |
| title_full_unstemmed | A Two-Step Approach to Uncertainty Quantification of Core Simulators |
| title_short | A Two-Step Approach to Uncertainty Quantification of Core Simulators |
| title_sort | two step approach to uncertainty quantification of core simulators |
| url | http://dx.doi.org/10.1155/2012/767096 |
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