EPJ Web Conf.
Volume 211, 2019WONDER-2018 – 5th International Workshop On Nuclear Data Evaluation for Reactor applications
|Number of page(s)||7|
|Section||Uncertainties And Covariance Matrices (Methodology and Impact on Reactor Calculations)|
|Published online||05 June 2019|
Covariance Matrices for Differential and Angle-Integrated Neutron-Induced Elastic and Inelastic Scattering Cross Sections of 56Fe
1 CEA, Cadarache, DEN/DER/SPRC/LEPh, 13108 Saint Paul Les Durance, France
2 Université Grenoble Alpes, I-MEP2, 38402 Saint Martin d’Hères, France
a Corresponding author: email@example.com
Published online: 5 June 2019
Correlations between neutron inelastic scatterings angular distributions are not included in the Joint Evaluated Fission and Fusion (JEFF) nuclear data library, while they are key quantities for uncertainty propagation of nuclear data. By reproducing the angle-integrated cross sections and uncertainties of JEFF-3.1.1, the present work obtains covariance matrix between high energy model parameters using the least square method implemented in the CONRAD code. With this matrix, it is possible to generate correlations between angle-integrated cross sections and angular distributions, which are usually presented by Legendre coefficients. As expected, strong correlations are found, for example, between the Legendre coefficients of elastic and first-level-inelastic scatterings and the angle-integrated total, elastic, total inelastic cross sections.
© The Authors, published by EDP Sciences, 2019
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