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Title: Approximate Techniques for Representing Nuclear Data Uncertainties

Abstract

Computational tools are available to utilize sensitivity and uncertainty (S/U) methods for a wide variety of applications in reactor analysis and criticality safety. S/U analysis generally requires knowledge of the underlying uncertainties in evaluated nuclear data, as expressed by covariance matrices; however, only a few nuclides currently have covariance information available in ENDF/B-VII. Recently new covariance evaluations have become available for several important nuclides, but a complete set of uncertainties for all materials needed in nuclear applications is unlikely to be available for several years at least. Therefore if the potential power of S/U techniques is to be realized for near-term projects in advanced reactor design and criticality safety analysis, it is necessary to establish procedures for generating approximate covariance data. This paper discusses an approach to create applications-oriented covariance data by applying integral uncertainties to differential data within the corresponding energy range.

Authors:
 [1];  [1];  [1];  [1]
  1. ORNL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
958811
DOE Contract Number:
DE-AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: Eighth International Topical Meeting on Nuclear Applications and Utilization of Accelerators, Pocatello, IN, USA, 20070730, 20070802
Country of Publication:
United States
Language:
English
Subject:
43 PARTICLE ACCELERATORS; ACCELERATORS; CRITICALITY; DESIGN; ENERGY RANGE; ISOTOPES; MATRICES; SAFETY; SAFETY ANALYSIS; SENSITIVITY; NUCLEAR DATA COLLECTIONS

Citation Formats

Williams, Mark L, Broadhead, Bryan L, Dunn, Michael E, and Rearden, Bradley T. Approximate Techniques for Representing Nuclear Data Uncertainties. United States: N. p., 2007. Web.
Williams, Mark L, Broadhead, Bryan L, Dunn, Michael E, & Rearden, Bradley T. Approximate Techniques for Representing Nuclear Data Uncertainties. United States.
Williams, Mark L, Broadhead, Bryan L, Dunn, Michael E, and Rearden, Bradley T. Mon . "Approximate Techniques for Representing Nuclear Data Uncertainties". United States. doi:.
@article{osti_958811,
title = {Approximate Techniques for Representing Nuclear Data Uncertainties},
author = {Williams, Mark L and Broadhead, Bryan L and Dunn, Michael E and Rearden, Bradley T},
abstractNote = {Computational tools are available to utilize sensitivity and uncertainty (S/U) methods for a wide variety of applications in reactor analysis and criticality safety. S/U analysis generally requires knowledge of the underlying uncertainties in evaluated nuclear data, as expressed by covariance matrices; however, only a few nuclides currently have covariance information available in ENDF/B-VII. Recently new covariance evaluations have become available for several important nuclides, but a complete set of uncertainties for all materials needed in nuclear applications is unlikely to be available for several years at least. Therefore if the potential power of S/U techniques is to be realized for near-term projects in advanced reactor design and criticality safety analysis, it is necessary to establish procedures for generating approximate covariance data. This paper discusses an approach to create applications-oriented covariance data by applying integral uncertainties to differential data within the corresponding energy range.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 2007},
month = {Mon Jan 01 00:00:00 EST 2007}
}

Conference:
Other availability
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