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Title: Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization

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.
Authors:
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Publication Date:
OSTI Identifier:
22436764
Resource Type:
Journal Article
Resource Relation:
Journal Name: Nuclear Data Sheets; Journal Volume: 123; Conference: International workshop on nuclear data covariances, Santa Fe, NM (United States), 28 Apr - 1 May 2014; Other Information: Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; AFTER-HEAT; BENCHMARKS; DATA COVARIANCES; FISSION PRODUCTS; INTEGRAL CROSS SECTIONS; NUCLEAR DATA COLLECTIONS; REACTOR SAFETY; SPENT FUELS; WATER COOLED REACTORS; WATER MODERATED REACTORS