Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1834943 | Nuclear Data Sheets | 2015 | 5 Pages |
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.
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Physical Sciences and Engineering
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Nuclear and High Energy Physics