Nuclear Data Uncertainty Propagation in Depletion Calculations Using Cross Section Uncertainties in Onegroup or Multigroup
Abstract
Several approaches have been developed in last decades to tackle nuclear data uncertainty propagation problems of burnup calculations. One approach proposed was the Hybrid Method, where uncertainties in nuclear data are propagated only on the depletion part of a burnup problem. Because only depletion is addressed, only onegroup cross sections are necessary, and hence, their collapsed onegroup uncertainties. This approach has been applied successfully in several advanced reactor systems like EFIT (ADSlike reactor) or ESFR (Sodium fast reactor) to assess uncertainties on the isotopic composition. However, a comparison with using multigroup energy structures was not carried out, and has to be performed in order to analyse the limitations of using onegroup uncertainties.
 Authors:
 Dpto. de Ingeníera Nuclear, Universidad Politécnica de Madrid, 28006 Madrid (Spain)
 (Spain)
 Publication Date:
 OSTI Identifier:
 22436762
 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; CROSS SECTIONS; DATA COVARIANCES; FAST REACTORS; ISOTOPES; NUCLEAR DATA COLLECTIONS; SODIUM COOLED REACTORS
Citation Formats
Díez, C.J., Email: cj.diez@upm.es, Cabellos, O., Instituto de Fusión Nuclear, Universidad Politécnica de Madrid, 28006 Madrid, and Martínez, J.S.. Nuclear Data Uncertainty Propagation in Depletion Calculations Using Cross Section Uncertainties in Onegroup or Multigroup. United States: N. p., 2015.
Web. doi:10.1016/J.NDS.2014.12.014.
Díez, C.J., Email: cj.diez@upm.es, Cabellos, O., Instituto de Fusión Nuclear, Universidad Politécnica de Madrid, 28006 Madrid, & Martínez, J.S.. Nuclear Data Uncertainty Propagation in Depletion Calculations Using Cross Section Uncertainties in Onegroup or Multigroup. United States. doi:10.1016/J.NDS.2014.12.014.
Díez, C.J., Email: cj.diez@upm.es, Cabellos, O., Instituto de Fusión Nuclear, Universidad Politécnica de Madrid, 28006 Madrid, and Martínez, J.S.. 2015.
"Nuclear Data Uncertainty Propagation in Depletion Calculations Using Cross Section Uncertainties in Onegroup or Multigroup". United States.
doi:10.1016/J.NDS.2014.12.014.
@article{osti_22436762,
title = {Nuclear Data Uncertainty Propagation in Depletion Calculations Using Cross Section Uncertainties in Onegroup or Multigroup},
author = {Díez, C.J., Email: cj.diez@upm.es and Cabellos, O. and Instituto de Fusión Nuclear, Universidad Politécnica de Madrid, 28006 Madrid and Martínez, J.S.},
abstractNote = {Several approaches have been developed in last decades to tackle nuclear data uncertainty propagation problems of burnup calculations. One approach proposed was the Hybrid Method, where uncertainties in nuclear data are propagated only on the depletion part of a burnup problem. Because only depletion is addressed, only onegroup cross sections are necessary, and hence, their collapsed onegroup uncertainties. This approach has been applied successfully in several advanced reactor systems like EFIT (ADSlike reactor) or ESFR (Sodium fast reactor) to assess uncertainties on the isotopic composition. However, a comparison with using multigroup energy structures was not carried out, and has to be performed in order to analyse the limitations of using onegroup uncertainties.},
doi = {10.1016/J.NDS.2014.12.014},
journal = {Nuclear Data Sheets},
number = ,
volume = 123,
place = {United States},
year = 2015,
month = 1
}

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