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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Published in | Science and technology of nuclear installations Vol. 2012; no. 2012; pp. 1 - 9 |
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Main Authors | , , , , , , , |
Format | Journal Article |
Language | English |
Published |
Cairo, Egypt
Hindawi Puplishing Corporation
01.01.2012
Hindawi Publishing Corporation Wiley |
Subjects | |
Online Access | Get full text |
ISSN | 1687-6075 1687-6083 |
DOI | 10.1155/2012/767096 |
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Abstract | 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. |
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AbstractList | 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. |
Author | Jessee, Matthew A. Velkov, Kiril Pautz, Andreas Collins, Benjamin S. Yankov, Artem Klein, Markus Zwermann, Winfried Downar, Thomas J. |
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Cites_doi | 10.3139/124.110148 |
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Contributor | Velkov, Kiril Pautz, Andreas Collins, Benjamin S Yankov, Artem Klein, Markus Jessee, Matthew A Zwermann, Winfried Downar, Thomas J |
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Copyright | Copyright © 2012 Artem Yankov et al. |
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References | Yankov A. Klein M. Jessee M. A. Zwermann W. Velkov K. Pautz A. Collins B. Downar T. Comparison of XSUSA and “two-step” approaches for full-core uncertainty quantification Proceedings of the International Conference on the Physics of Reactors (PHYSOR '12) April 2012 Knoxville, Tenn, USA 16 Klein M. Gallner L. Krzykacz-Hausmann B. Pautz A. Velkov K. Zwermann W. Interaction of loading pattern and nuclear data uncertainties in reactor core calculations Proceedings of the International Conference on the Physics of Reactors (PHYSOR '12) April 2012 Knoxville, Tenn, USA Pasichnyk I. Klein M. Velkov K. Zwermann W. Pautz A. Nuclear data uncertainties by the PWR MOX/UO2 core rod ejection benchmark Proceedings of the International Conference on the Physics of Reactors (PHYSOR '12) April 2012 Knoxville, Tenn, USA Bevington P. R. Robinson K. Data Reduction and Error Analysis for the Physical Sciences 2003 Boston, Mass, USA McGraw-Hill Krzykacz B. Hofer E. Kloos M. A software system for probabilistic uncertainty and sensitivity analysis of results from computer models Proceedings of the International Conference on Probabilistic Safety Assessment and Management (PSAM '94) 1994 San Diego, Calif, USA Williams M. Wiarda D. Smith H. Jessee M. A. Rearden B. T. Zwermann W. Klein M. Pautz A. Krzykacz-Hausmann B. Gallner L. Development of a statistical sampling method for uncertainty analysis with scale Proceedings of the International Conference on the Physics of Reactors (PHYSOR '12) April 2012 Knoxville, Tenn, USA Jessee M. A. Williams M. L. DeHart M. D. Development of generalized perturbation theory capability within the scale code package Proceedings of the International Conference on Mathematics, Computational Methods, and Reactor Physics (M&C '09) May 2009 New York, NY, USA Saratoga Springs (2) 2011; 76 Langenbuch S. Velkov K. Overview on the development and application of the coupled code system ATHLET—QUABBOX/CUBBOX Proceedings of the Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications September 2005 Avignon, France Ivanov K. Beam T. M. Baratta A. J. Irani A. Trikouros N. Pressurised water reactor Main Steam Line Break (MSLB) benchmark 1999 NEA/NSC/DOC(99)8 Nuclear Energy Agency Jessee M. A. Cross section adjustment techniques for BWR adaptive simulation [Dissertation] 2008 Raleigh, NC, USA North Carolina State University Williams M. Perturbation theory for nuclear reactor analysis CRC Handbook of Nuclear Reactor Calculations 1986 3 63 188 (17) 1921; 1 Downar T. Xu Y. Seker V. PARCSv3. 0 Theory Manual UM-NERS-09-001, October 2009 Yankov A. Collins B. Jessee M. A. Downar T. A generalized adjoint approach for quantifying reflector assembly discontinuity factor uncertainties Proceedings of the International Conference on the Physics of Reactors (PHYSOR '12) April 2012 Knoxville, Tenn, USA Ivanov K. Avramova M. Kodeli I. Sartori E. Benchmark for Uncertainty Analysis in Modeling (UAM) for Design, Operation and Safety Analysis of LWRs 2007 2nd Nuclear Energy Agency Rep. NEA/NSC/DOC(2007)23 SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design 2011 Oak Ridge, Tenn, USA Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-785 ORNL/TM-2005/39, Version 6. 1 Williams M. Jessee M. A. Ellis R. Rearden B. Sensitivity and uncertainty analysis for OECD UAM benchmark of peach bottom BWR Proceedings of the 4th Uncertainty Analysis in Modelling Benchmark Meeting April 2010 Pisa, Italy (7) 2011 (1) 2007 (8) 2003 (12) 1986; 3 |
References_xml | – reference: Williams M. Perturbation theory for nuclear reactor analysis CRC Handbook of Nuclear Reactor Calculations 1986 3 63 188 – reference: Jessee M. A. Williams M. L. DeHart M. D. Development of generalized perturbation theory capability within the scale code package Proceedings of the International Conference on Mathematics, Computational Methods, and Reactor Physics (M&C '09) May 2009 New York, NY, USA Saratoga Springs – reference: Langenbuch S. Velkov K. Overview on the development and application of the coupled code system ATHLET—QUABBOX/CUBBOX Proceedings of the Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications September 2005 Avignon, France – reference: Jessee M. A. Cross section adjustment techniques for BWR adaptive simulation [Dissertation] 2008 Raleigh, NC, USA North Carolina State University – reference: Ivanov K. Beam T. M. Baratta A. J. Irani A. Trikouros N. Pressurised water reactor Main Steam Line Break (MSLB) benchmark 1999 NEA/NSC/DOC(99)8 Nuclear Energy Agency – reference: Williams M. Wiarda D. Smith H. Jessee M. A. Rearden B. T. Zwermann W. Klein M. Pautz A. Krzykacz-Hausmann B. Gallner L. Development of a statistical sampling method for uncertainty analysis with scale Proceedings of the International Conference on the Physics of Reactors (PHYSOR '12) April 2012 Knoxville, Tenn, USA – ident: 16 article-title: A statistical sampling method for uncertainty analysis with SCALE and XSUSA – volume: 1 start-page: 3 year: 1921 end-page: 32 ident: 17 article-title: On the ‘probable error’ of a coefficient of correlation deduced from a small sample – reference: Bevington P. R. Robinson K. Data Reduction and Error Analysis for the Physical Sciences 2003 Boston, Mass, USA McGraw-Hill – reference: Pasichnyk I. Klein M. Velkov K. Zwermann W. Pautz A. Nuclear data uncertainties by the PWR MOX/UO2 core rod ejection benchmark Proceedings of the International Conference on the Physics of Reactors (PHYSOR '12) April 2012 Knoxville, Tenn, USA – reference: Downar T. Xu Y. Seker V. PARCSv3. 0 Theory Manual UM-NERS-09-001, October 2009 – reference: Ivanov K. Avramova M. Kodeli I. Sartori E. Benchmark for Uncertainty Analysis in Modeling (UAM) for Design, Operation and Safety Analysis of LWRs 2007 2nd Nuclear Energy Agency Rep. NEA/NSC/DOC(2007)23 – reference: SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design 2011 Oak Ridge, Tenn, USA Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-785 ORNL/TM-2005/39, Version 6. 1 – reference: Yankov A. Klein M. Jessee M. A. Zwermann W. Velkov K. Pautz A. Collins B. Downar T. Comparison of XSUSA and “two-step” approaches for full-core uncertainty quantification Proceedings of the International Conference on the Physics of Reactors (PHYSOR '12) April 2012 Knoxville, Tenn, USA – reference: Klein M. Gallner L. Krzykacz-Hausmann B. Pautz A. Velkov K. Zwermann W. Interaction of loading pattern and nuclear data uncertainties in reactor core calculations Proceedings of the International Conference on the Physics of Reactors (PHYSOR '12) April 2012 Knoxville, Tenn, USA – reference: Williams M. Jessee M. A. Ellis R. Rearden B. Sensitivity and uncertainty analysis for OECD UAM benchmark of peach bottom BWR Proceedings of the 4th Uncertainty Analysis in Modelling Benchmark Meeting April 2010 Pisa, Italy – volume: 76 start-page: 174 issue: 3 year: 2011 end-page: 178 ident: 2 article-title: Influence of nuclear data uncertainties on reactor core calculations – reference: Krzykacz B. Hofer E. Kloos M. A software system for probabilistic uncertainty and sensitivity analysis of results from computer models Proceedings of the International Conference on Probabilistic Safety Assessment and Management (PSAM '94) 1994 San Diego, Calif, USA – reference: Yankov A. Collins B. Jessee M. A. Downar T. A generalized adjoint approach for quantifying reflector assembly discontinuity factor uncertainties Proceedings of the International Conference on the Physics of Reactors (PHYSOR '12) April 2012 Knoxville, Tenn, USA – volume: 1 start-page: 3 year: 1921 ident: 17 publication-title: Metron – volume: 76 start-page: 174 issue: 3 year: 2011 ident: 2 publication-title: Kerntechnik doi: 10.3139/124.110148 – year: 2007 ident: 1 – year: 2011 ident: 7 – volume: 3 start-page: 63 volume-title: Perturbation theory for nuclear reactor analysis year: 1986 ident: 12 – year: 2003 ident: 8 – ident: 16 |
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Title | A Two-Step Approach to Uncertainty Quantification of Core Simulators |
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