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Title: Template for estimating uncertainties of measured neutron-induced fission cross-sections

Abstract

A template for estimating uncertainties (unc.) of measured neutron-induced fission, (n,f), cross-sections (cs) is presented. This preliminary template not only lists all expected unc. sources but also supplies ranges of unc., estimates for correlations between unc. of the same and different experiments which can be used if the information is nonexistent. If this template is applied systematically when estimating experimental covariances for an evaluation, it may help in pinpointing missing unc. for individual datasets, identifying unreasonably low unc., and estimating correlations between different experimental datasets. Thus, a detailed unc. estimate – usually, a time-intensive procedure – can be undertaken more consistently and efficiently. As an example, it is shown that unc. and correlations of 239Pu(n,f) by Merla et al. [Proceedings of the Conference on Nuclear Data for Science and Technology 1991 Jülich (Springer-Verlag, Berlin, 1992) pp. 510–513], which are questionably low in the GMA database underlying the neutron cs standards evaluations, are distinctly larger at 14.7 MeV and more strongly correlated if this template is used for reestimating the associated covariances.

Authors:
ORCiD logo [1];  [1]; ORCiD logo [1]; ORCiD logo [1];  [2];  [1];  [3]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Argonne National Laboratory, Coronado, CA (United States)
  3. International Atomic Energy Agency, Vienna (Austria)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1489948
Report Number(s):
LA-UR-17-29963
Journal ID: ISSN 2491-9292
Grant/Contract Number:  
89233218CNA000001; AC52-06NA25396
Resource Type:
Accepted Manuscript
Journal Name:
EPJ Nuclear Sciences and Technologies
Additional Journal Information:
Journal Volume: 4; Journal ID: ISSN 2491-9292
Country of Publication:
United States
Language:
English
Subject:
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY

Citation Formats

Neudecker, Denise, Hejnal, Brooke Ellen, Tovesson, Fredrik, White, Morgan Curtis, Smith, Donald L., Vaughan, Diane Elizabeth, and Capote, R. Template for estimating uncertainties of measured neutron-induced fission cross-sections. United States: N. p., 2018. Web. doi:10.1051/epjn/2018026.
Neudecker, Denise, Hejnal, Brooke Ellen, Tovesson, Fredrik, White, Morgan Curtis, Smith, Donald L., Vaughan, Diane Elizabeth, & Capote, R. Template for estimating uncertainties of measured neutron-induced fission cross-sections. United States. doi:10.1051/epjn/2018026.
Neudecker, Denise, Hejnal, Brooke Ellen, Tovesson, Fredrik, White, Morgan Curtis, Smith, Donald L., Vaughan, Diane Elizabeth, and Capote, R. Wed . "Template for estimating uncertainties of measured neutron-induced fission cross-sections". United States. doi:10.1051/epjn/2018026. https://www.osti.gov/servlets/purl/1489948.
@article{osti_1489948,
title = {Template for estimating uncertainties of measured neutron-induced fission cross-sections},
author = {Neudecker, Denise and Hejnal, Brooke Ellen and Tovesson, Fredrik and White, Morgan Curtis and Smith, Donald L. and Vaughan, Diane Elizabeth and Capote, R.},
abstractNote = {A template for estimating uncertainties (unc.) of measured neutron-induced fission, (n,f), cross-sections (cs) is presented. This preliminary template not only lists all expected unc. sources but also supplies ranges of unc., estimates for correlations between unc. of the same and different experiments which can be used if the information is nonexistent. If this template is applied systematically when estimating experimental covariances for an evaluation, it may help in pinpointing missing unc. for individual datasets, identifying unreasonably low unc., and estimating correlations between different experimental datasets. Thus, a detailed unc. estimate – usually, a time-intensive procedure – can be undertaken more consistently and efficiently. As an example, it is shown that unc. and correlations of 239Pu(n,f) by Merla et al. [Proceedings of the Conference on Nuclear Data for Science and Technology 1991 Jülich (Springer-Verlag, Berlin, 1992) pp. 510–513], which are questionably low in the GMA database underlying the neutron cs standards evaluations, are distinctly larger at 14.7 MeV and more strongly correlated if this template is used for reestimating the associated covariances.},
doi = {10.1051/epjn/2018026},
journal = {EPJ Nuclear Sciences and Technologies},
number = ,
volume = 4,
place = {United States},
year = {2018},
month = {11}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record

Figures / Tables:

Table 1 Table 1: A list of unc. sources typically encountered in (n,f) fission cs measurements is provided together with a range of unc., their correlations, and comments on possible cross-correlations between unc. of different experimental datasets as a rough estimate if no information is provided for a specific experiment.

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Works referenced in this record:

Evaluation of the Neutron Data Standards
journal, February 2018


A Monte Carlo computer program for the transport of energetic ions in amorphous targets
journal, August 1980


The Need for Precise and Well-documented Experimental Data on Prompt Fission Neutron Spectra from Neutron-induced Fission of 239Pu
journal, January 2016


A time projection chamber for high accuracy and precision fission cross-section measurements
journal, September 2014

  • Heffner, M.; Asner, D. M.; Baker, R. G.
  • Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 759
  • DOI: 10.1016/j.nima.2014.05.057

    Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.