Open Access
ND 2007
Article Number 071
Number of page(s) 6
Section Evaluation of covariance matrices
Published online 17 June 2008
International Conference on Nuclear Data for Science and Technology 2007
DOI: 10.1051/ndata:07339

Evaluation of the covariance matrix of neutronic cross sections with the Backward-Forward Monte Carlo method

E. Bauge, S. Hilaire and P. Dossantos-Uzarralde

CEA DAM Île-de-France, Département de Physique Théorique et Appliquée, Service de Physique Nucléaire, BP. 12, 91680 Bruyères-le-Châtel, France

Published online: 21 May 2008

With the advent of modern nuclear reaction modeling codes, it has become possible to produce evaluated data from model calculations only. However, the process of estimating of the uncertainties associated with nuclear data evaluated by model calculations is not as well defined as the assessment of uncertainties resulting from an experimental-data-driven evaluation process. In this paper, we propose a method, based on the Monte Carlo sampling of the model parameter space, that allows for a quantitative estimation the covariance matrix of the model parameters, as well as that of the derived cross sections. Constrains from experimental data are included by building a probability density function of the model parameter space as a function of the generalized χ2 that estimates the calculation-data mismatch. The uncertainties of the model parameters are then propagated to the derived cross sections, whose distribution is analyzed in terms of a covariance matrix. As an example, this method is applied to the models used in the nuclear reaction code TALYS and a full covariance matrix for the evaluated cross sections of the n+89Y system is obtained.

© CEA 2008

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