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

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. | Template for estimating uncertainties of measured neutron-induced fission cross-sections EPJ Nuclear Sci. Technol. 4 21 2018 Nuclear Sciences D. Neudecker et al. published by EDP Sciences 2018 amp Technologies https epjn 2018026 Available online at https REGULAR ARTICLE Template for estimating uncertainties of measured neutron-induced fission cross-sections Denise Neudecker1 Brooke Hejnal1 Fredrik Tovesson1 Morgan C. White1 Donald L. Smith2 Diane Vaughan1 and R. Capote3 1 Los Alamos National Laboratory Los Alamos NM 87545 USA 2 Argonne National Laboratory Coronado CA 92118 USA retired 3 NAPC-Nuclear Data Section International Atomic Energy Agency Vienna 1400 Austria Received 31 October 2017 Received in final form 29 January 2018 Accepted 14 May 2018 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 MeV and more strongly correlated if this template is used for reestimating the associated covariances. 1 Introduction One example why

• Năng lượng
• Neutron induced fission
• Neutron induced fission cross sections
• Nuclear Data for Science and Technology
• Generalized least squares analysis
• The GMA database