Sensitivity and a priori uncertainty analysis of the CFRMF central flux spectrum

Abstract

The Coupled Fast Reactivity Measurements Facility (CFRMF), located at the Idaho National Engineering Laboratory, is a zoned-core critical assembly with a fast-neutron-spectrum zone in the center of an enriched /sup 235/U, water-moderated thermal driver. An accurate knowledge of the central neutron spectrum is important to data-testing analyses which utilize integral reaction-rate data measured for samples placed in the CFRMF field. The purpose of this paper is to present the results of a study made with the AMPX-II and FORSS code systems to deterine the central-spectrum flux covariance matrix due to uncertainties and correlations in the nuclear data for the materials which comprise the facility