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 inScience and technology of nuclear installations Vol. 2012; no. 2012; pp. 1 - 9
Main Authors Yankov, Artem, Collins, Benjamin S., Klein, Markus, Jessee, Matthew A., Zwermann, Winfried, Velkov, Kiril, Pautz, Andreas, Downar, Thomas J.
Format Journal Article
LanguageEnglish
Published Cairo, Egypt Hindawi Puplishing Corporation 01.01.2012
Hindawi Publishing Corporation
Wiley
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ISSN1687-6075
1687-6083
DOI10.1155/2012/767096

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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.
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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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
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References_xml – reference: Williams M. Perturbation theory for nuclear reactor analysis CRC Handbook of Nuclear Reactor Calculations 1986 3 63 188
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– 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
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– 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
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– 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
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SubjectTerms Computation
Cross sections
Mathematical models
Propagation
Sampling
Simulators
Stochasticity
Uncertainty
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Title A Two-Step Approach to Uncertainty Quantification of Core Simulators
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