Extension of SCALE/Sampler's sensitivity analysis

Friederike Bostelmann; Dorothea Wiarda; Goran Arbanas; William A. Wieselquist

doi:10.1016/j.anucene.2021.108641

Extension of SCALE/Sampler's sensitivity analysis

Friederike Bostelmann, Dorothea Wiarda, Goran Arbanas, William A. Wieselquist

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6 Scopus citations

Abstract

Nuclear data are a major source of uncertainties in reactor physics calculations. The propagation of nuclear data uncertainties to important system responses is instrumental when determining appropriate safety margins in reactor safety analyses. It is also important to understand the major contributors to the observed uncertainties to make recommendations for further measurements and evaluations and aid in the understanding of the studied system. The SCALE code system allows for nuclear data uncertainty analysis based on the random sampling approach as implemented in SCALE's Sampler sequence. Sampler was recently extended by a sensitivity analysis in terms of the calculation of two correlation-based sensitivity indices. This analysis allows for the identification of the top contributing nuclear reactions to any analyzed output uncertainty. This paper presents the sensitivity indices, along with their interpretation and limitations. It demonstrates the application in an eigenvalue and decay heat analysis for a boiling water reactor fuel assembly.

Original language	English
Article number	108641
Journal	Annals of Nuclear Energy
Volume	165
DOIs	https://doi.org/10.1016/j.anucene.2021.108641
State	Published - Jan 2022

Funding

This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan). This work was supported by the US Nuclear Regulatory Commission Office of Nuclear Regulatory Research and the US Department of Energy Nuclear Criticality Safety Program. Dr. Ugur Mertyurek’s (ORNL) comments and review of the implementation are much appreciated. The authors would like to thank Dr. Germina Ilas (ORNL) for providing her BWR fuel assembly model for the analysis in this paper. The discussions about XSUSA’s sensitivity analysis with Dr. Winfried Zwermann (GRS), Prof. Andreas Pautz (Ècole polytechnique fèdèrale de Lausanne), and Dr. Bernard Krzykacz-Hausmann (GRS) are also much appreciated. This work was supported by the US Nuclear Regulatory Commission Office of Nuclear Regulatory Research and the US Department of Energy Nuclear Criticality Safety Program. Dr. Ugur Mertyurek's (ORNL) comments and review of the implementation are much appreciated. The authors would like to thank Dr. Germina Ilas (ORNL) for providing her BWR fuel assembly model for the analysis in this paper. The discussions about XSUSA's sensitivity analysis with Dr. Winfried Zwermann (GRS), Prof. Andreas Pautz (?cole polytechnique f?d?rale de Lausanne), and Dr. Bernard Krzykacz-Hausmann (GRS) are also much appreciated.

Keywords

Correlation coefficient
Nuclear data
Random sampling
SCALE
Sampler
Sensitivity analysis

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10.1016/j.anucene.2021.108641

Cite this

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title = "Extension of SCALE/Sampler's sensitivity analysis",

abstract = "Nuclear data are a major source of uncertainties in reactor physics calculations. The propagation of nuclear data uncertainties to important system responses is instrumental when determining appropriate safety margins in reactor safety analyses. It is also important to understand the major contributors to the observed uncertainties to make recommendations for further measurements and evaluations and aid in the understanding of the studied system. The SCALE code system allows for nuclear data uncertainty analysis based on the random sampling approach as implemented in SCALE's Sampler sequence. Sampler was recently extended by a sensitivity analysis in terms of the calculation of two correlation-based sensitivity indices. This analysis allows for the identification of the top contributing nuclear reactions to any analyzed output uncertainty. This paper presents the sensitivity indices, along with their interpretation and limitations. It demonstrates the application in an eigenvalue and decay heat analysis for a boiling water reactor fuel assembly.",

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AB - Nuclear data are a major source of uncertainties in reactor physics calculations. The propagation of nuclear data uncertainties to important system responses is instrumental when determining appropriate safety margins in reactor safety analyses. It is also important to understand the major contributors to the observed uncertainties to make recommendations for further measurements and evaluations and aid in the understanding of the studied system. The SCALE code system allows for nuclear data uncertainty analysis based on the random sampling approach as implemented in SCALE's Sampler sequence. Sampler was recently extended by a sensitivity analysis in terms of the calculation of two correlation-based sensitivity indices. This analysis allows for the identification of the top contributing nuclear reactions to any analyzed output uncertainty. This paper presents the sensitivity indices, along with their interpretation and limitations. It demonstrates the application in an eigenvalue and decay heat analysis for a boiling water reactor fuel assembly.

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Extension of SCALE/Sampler's sensitivity analysis

Abstract

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Keywords

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