Assessment of the $^{153}$Eu and $^{154}$Eu neutron capture cross sections from the Integral Data Assimilation of spent nuclear fuel experiments - Archive ouverte HAL Access content directly
Journal Articles Annals of Nuclear Energy Year : 2018

Assessment of the $^{153}$Eu and $^{154}$Eu neutron capture cross sections from the Integral Data Assimilation of spent nuclear fuel experiments

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Abstract

The purpose of this paper is to make the most of a large set of used nuclear fuel experiments for determining integral trends on the $^{153}$Eu(n,$\gamma$) and $^{154}$Eu(n,$\gamma$) reactions cross sections. The assimilation of the integral trends is based on a linear least-square fitting procedure relying on the Bayes’ theorem. Realistic uncertainties are obtained thanks to a marginalization technique. The method is applied to the $^{153}$Eu and $^{154}$Eu capture cross sections recommended in the evaluated nuclear data library JEFF-3.1.1. Our results indicate an underestimation of both capture cross-sections of approximately 4.9% and 7.1%, respectively. For $^{153}$Eu, our study suggests to increase the capture resonance integral from I$_0$=1409 barns to I$_0$=1502 $\pm$ 68 barns. This trend is consistent with the capture resonance integral I$_0$=1560 barns obtained from recent time-of-flight measurements carried out at the Renssealer Polytechnic Institute. The trend obtained in this work on $^{154}$Eu capture cross section is also consistent with a recent analysis carried out on ENDF/B-VII.1, for which $^{154}$Eu capture cross section is very similar to JEFF-3.1.1, therefore confirming its underestimation.
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Dates and versions

cea-02339612 , version 1 (04-11-2019)

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  • HAL Id : cea-02339612 , version 1

Cite

A. Rizzo, C. Vaglio-Gaudard, G. Noguere, R. Eschbach, J-F. Martin, et al.. Assessment of the $^{153}$Eu and $^{154}$Eu neutron capture cross sections from the Integral Data Assimilation of spent nuclear fuel experiments. Annals of Nuclear Energy, 2018, 124, pp.524-532. ⟨cea-02339612⟩

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