Issue |
EPJ Web Conf.
Volume 239, 2020
ND 2019: International Conference on Nuclear Data for Science and Technology
|
|
---|---|---|
Article Number | 11006 | |
Number of page(s) | 4 | |
Section | Evaluation Methodology | |
DOI | https://doi.org/10.1051/epjconf/202023911006 | |
Published online | 30 September 2020 |
https://doi.org/10.1051/epjconf/202023911006
New 23Na evaluation in the resolved resonance range taking into account both differential and double differential experiments
CEA/DER/SPRC/LEPh, CEA Cadarache, 13108 Saint-Paul-lez-Durance, FRANCE
* e-mail: pierre.tamagno@cea.fr
Published online: 30 September 2020
In 2012 CEA produced a entire new evaluation of sodium nuclear data for the release of the JEFF-3.2 evaluated nuclear data library. During the evaluation process performed with the CONRAD code, several differential measurements (total and discrete inelastic cross-sections) have been used. However double differential data (elastic angular distribution) that were yet available in the EXFOR database were not incorporated in the analysis at that time. The experimental elastic angular distribution were discarded because of it was impossible to obtain a good agreement for both angle-integrated cross-sections and double differential ones. The underlying cause of this disagreement is expected to be due to the attribution of quantum numbers to resonance and related channel amplitudes. Indeed these numbers are imposed during the analysis but impact differently angular distributions and angle-integrated cross-sections. An automated search for an accurate set of quantum numbers has been implemented in order to produce a reliable quantum numbers set. In this paper we present a new evaluation of Na-23 taking into account both differential and double differential measurements. The analysis performed with the CONRAD code reached the level of agreement with experimental data for the total and inelastic cross-sections but this time with a significant improvement for the elastic angular distributions. This new evaluation produced in the ENDF-6 format has then been tested and validated on critical facilities calculation (MASURCA and ZPPR) in different configurations (nominal and voided) in order to assess its performances.
© The Authors, published by EDP Sciences, 2020
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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