Extension of SCALE/Sampler's sensitivity analysis. (January 2022)

• Record Type: Journal Article
• Authors: Bostelmann, Friederike; Wiarda, Dorothea; Arbanas, Goran; Wieselquist, William A.
• Is Part Of: Annals of nuclear energy. Volume 165(2022)
• Publication Date: 2022-01
• Subjects: Sensitivity analysis -- Correlation coefficient -- Nuclear data -- Random sampling -- SCALE -- Sampler; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2021.108641
• Languages: English
• ISSNs: 0306-4549

Abstract

Highlights: Sensitivity analysis capability is added to SCALE's Sampler sequence. Identification of top contributing nuclear reactions to uncertainty is enabled. Mathematical description, interpretation, and limitations of new indices are provided. Demonstration is performed for BWR assembly eigenvalue and decay heat 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.