Article ID Journal Published Year Pages File Type
1834943 Nuclear Data Sheets 2015 5 Pages PDF
Abstract

A new covariance data library based on ENDF/B-VII.1 was recently processed for the SCALE nuclear analysis code system. The multigroup covariance data are discussed here, along with testing and application results for critical benchmark experiments. The cross section covariance library, along with covariances for fission product yields and decay data, is used to compute uncertainties in the decay heat produced by a burned reactor fuel assembly.

Related Topics
Physical Sciences and Engineering Physics and Astronomy Nuclear and High Energy Physics