Work plan for improving the DARWIN2.3 depleted material balance calculation of nuclides of interest for the fuel cycle

• Published in: EPJ Web of conferences Vol. 146; p. 9030
• Main Authors: Rizzo, Axel, Vaglio-Gaudard, Claire, Martin, Julie-Fiona, Noguère, Gilles, Eschbach, Romain
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Les Ulis EDP Sciences 01-01-2017
• Series: ND 2016: International Conference on Nuclear Data for Science and Technology, Bruges, Belgique
• Subjects: Boiling water reactors; Depletion; Fast nuclear reactors; Fuel cycles; Light water reactors; Material balance; Mathematical analysis; Nuclear Experiment; Nuclear fuels; Nuclear Theory; Nuclides; Physics; Uncertainty; Validation; DARWIN; TRIPOLI; Fuel cycle; Nuclear Data; Depletion calculation
• ISSN: 2100-014X; 2101-6275; 2100-014X
• DOI: 10.1051/epjconf/201714609030

DARWIN2.3 is the reference package used for fuel cycle applications in France. It solves the Boltzmann and Bateman equations in a coupling way, with the European JEFF-3.1.1 nuclear data library, to compute the fuel cycle values of interest. It includes both deterministic transport codes APOLLO2 (for light water reactors) and ERANOS2 (for fast reactors), and the DARWIN/PEPIN2 depletion code, each of them being developed by CEA/DEN with the support of its industrial partners. The DARWIN2.3 package has been experimentally validated for pressurized and boiling water reactors, as well as for sodium fast reactors; this experimental validation relies on the analysis of post-irradiation experiments (PIE). The DARWIN2.3 experimental validation work points out some isotopes for which the depleted concentration calculation can be improved. Some other nuclides have no available experimental validation, and their concentration calculation uncertainty is provided by the propagation of a priori nuclear data uncertainties. This paper describes the work plan of studies initiated this year to improve the accuracy of the DARWIN2.3 depleted material balance calculation concerning some nuclides of interest for the fuel cycle.