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Title: Nuclear Data and Measurement Series - a method to construct covariance files in ENDF/B format for criticality safety applications.

Abstract

Argonne National Laboratory is providing support for a criticality safety analysis project that is being performed at Oak Ridge National Laboratory. The ANL role is to provide the covariance information needed by ORNL for this project. The ENDF/B-V evaluation is being used for this particular criticality analysis. In this evaluation, covariance information for several isotopes or elements of interest to this analysis is either not given or needs to be reconsidered. For some required materials, covariance information does not exist in ENDF/B-V: {sup 233}U, {sup 236}U, Zr, Mg, Gd, and Hf. For others, existing covariance information may need to be re-examined in light of the newer ENDF/B-V evaluation and recent experimental data. In this category are the following materials: {sup 235}U, {sup 238}U, {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, Fe, H, C, N, O, Al, Si, and B. A reasonable estimation of the fractional errors for various evaluated neutron cross sections from ENDF/B-V can be based on the comparisons between the major more recent evaluations including ENDF/B-VI, JENDL3.2, BROND2.2, and JEF2.2, as well as a careful examination of experimental data. A reasonable method to construct correlation matrices is proposed here. Coupling both of these considerations suggests a method to constructmore » covariances files in ENDF/B format that can be used to express uncertainties for specific ENDF/B-V cross sections.« less

Authors:
;
Publication Date:
Research Org.:
Argonne National Lab., IL (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
12069
Report Number(s):
ANL/NDM-148
TRN: US0102344
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 30 Jul 1999
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; CRITICALITY; CROSS SECTIONS; SAFETY ANALYSIS; DATA COVARIANCES; URANIUM 233; URANIUM 236; ZIRCONIUM; MAGNESIUM; GADOLINIUM; HAFNIUM; URANIUM 235; URANIUM 238; PLUTONIUM 239; PLUTONIUM 240; PLUTONIUM 241; IRON; HYDROGEN; CARBON; NITROGEN; OXYGEN; ALUMINIUM; SILICON; BORON

Citation Formats

Naberejnev, D G, and Smith, D L. Nuclear Data and Measurement Series - a method to construct covariance files in ENDF/B format for criticality safety applications.. United States: N. p., 1999. Web. doi:10.2172/12069.
Naberejnev, D G, & Smith, D L. Nuclear Data and Measurement Series - a method to construct covariance files in ENDF/B format for criticality safety applications.. United States. doi:10.2172/12069.
Naberejnev, D G, and Smith, D L. Fri . "Nuclear Data and Measurement Series - a method to construct covariance files in ENDF/B format for criticality safety applications.". United States. doi:10.2172/12069. https://www.osti.gov/servlets/purl/12069.
@article{osti_12069,
title = {Nuclear Data and Measurement Series - a method to construct covariance files in ENDF/B format for criticality safety applications.},
author = {Naberejnev, D G and Smith, D L},
abstractNote = {Argonne National Laboratory is providing support for a criticality safety analysis project that is being performed at Oak Ridge National Laboratory. The ANL role is to provide the covariance information needed by ORNL for this project. The ENDF/B-V evaluation is being used for this particular criticality analysis. In this evaluation, covariance information for several isotopes or elements of interest to this analysis is either not given or needs to be reconsidered. For some required materials, covariance information does not exist in ENDF/B-V: {sup 233}U, {sup 236}U, Zr, Mg, Gd, and Hf. For others, existing covariance information may need to be re-examined in light of the newer ENDF/B-V evaluation and recent experimental data. In this category are the following materials: {sup 235}U, {sup 238}U, {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, Fe, H, C, N, O, Al, Si, and B. A reasonable estimation of the fractional errors for various evaluated neutron cross sections from ENDF/B-V can be based on the comparisons between the major more recent evaluations including ENDF/B-VI, JENDL3.2, BROND2.2, and JEF2.2, as well as a careful examination of experimental data. A reasonable method to construct correlation matrices is proposed here. Coupling both of these considerations suggests a method to construct covariances files in ENDF/B format that can be used to express uncertainties for specific ENDF/B-V cross sections.},
doi = {10.2172/12069},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1999},
month = {7}
}