Advancing Inverse Sensitivity/Uncertainty Methods for Nuclear Fuel Cycle Applications

doi:10.1016/j.nds.2014.12.009

Nuclear Data Sheets

Volume 123, January 2015, Pages 51-56

https://doi.org/10.1016/j.nds.2014.12.009 Get rights and content

Abstract

The inverse sensitivity/uncertainty quantification (IS/UQ) method has recently been implemented in the Inverse Sensitivity/UnceRtainty Estimator (INSURE) module of the AMPX cross section processing system [M.E. Dunn and N.M. Greene, “AMPX-2000: A Cross-Section Processing System for Generating Nuclear Data for Criticality Safety Applications,” Trans. Am. Nucl. Soc. 86, 118–119 (2002)]. The IS/UQ method aims to quantify and prioritize the cross section measurements along with uncertainties needed to yield a given nuclear application(s) target response uncertainty, and doing this at a minimum cost. Since in some cases the extant uncertainties of the differential cross section data are already near the limits of the present-day state-of-the-art measurements, requiring significantly smaller uncertainties may be unrealistic. Therefore, we have incorporated integral benchmark experiments (IBEs) data into the IS/UQ method using the generalized linear least-squares method, and have implemented it in the INSURE module. We show how the IS/UQ method could be applied to systematic and statistical uncertainties in a self-consistent way and how it could be used to optimize uncertainties of IBEs and differential cross section data simultaneously. We itemize contributions to the cost of differential data measurements needed to define a realistic cost function.

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Citation Excerpt :
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^☆: This manuscript has been authored by UT-Battelle LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes.

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Advancing Inverse Sensitivity/Uncertainty Methods for Nuclear Fuel Cycle Applications☆

Abstract

Nucl. Data Sheets

J. Korean Phys. Soc.

ANS Annual Meeting

AMPX-2000: A Cross-Section Processing System for Generating Nuclear Data for Criticality Safety Applications

Trans. Am. Nucl. Soc.

Updated Users' Guide for SAMMY: Multilevel R-matrix Fits to Neutron Data Using Bayes' Equations

SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design

Planning an Optimum Set of Microscopic Experiments and Evaluations to Obtain a Given Accuracy in Reactor Parameter Calculations (English translation of a Russian original)