Journal
ANNALS OF NUCLEAR ENERGY
Volume 165, Issue -, Pages -Publisher
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.anucene.2021.108641
Keywords
Sensitivity analysis; Correlation coefficient; Nuclear data; Random sampling; SCALE; Sampler
Categories
Funding
- US Nuclear Regulatory Com-mission Office of Nuclear Regulatory Research
- US Depart-ment of Energy Nuclear Criticality Safety Program
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Nuclear data uncertainties play a significant role in reactor physics calculations, and conducting sensitivity analysis to identify major contributors can guide further measurements and evaluations, enhancing the understanding of the studied system.
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. (c) 2021 The Author(s). Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
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