Development of Cross-section Uncertainty Library for Core Simulators - I: Theories

Abstract

Uncertainty quantification has been recognized by the community as an essential component of best-estimate reactor analysis simulation because it provides a measure by which the credibility of the simulation can be assessed. The overarching objective of our research is to establish a framework that can automate the propagation, prioritization, mapping, and reduction of uncertainties for reactor analysis core simulation. Recognizing the computational taxing nature of this endeavor, this manuscript provides a comprehensive overview of and further develops a compressed representation of the uncertainty space in order to render the overall process computationally feasible in routine day-to-day calculations. In this manuscript, we focus only on nuclear data uncertainties as the sources of uncertainties, and the quantities of interest are core attributes such as eigenvalue and power distribution in steady state core follow calculations. This paper is the first part of the manuscript covering the theories to develop the cross-section uncertainty library for core uncertainty characteristics.