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Propagation of Nuclear Data Uncertainties in Transmutation Calculations Using ACAB Code
O. Cabellos,N. Garcia-Herranz,Carlos J. Diez de la Obra,R. Alvarez-Cascos,J. Sanz,F. Ogando,P. Sauvan 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
The assessment of the accuracy of parameters related to the reactor core performance (e.g. keff) and fuel cycle (e.g. isotopic evolution/transmutation) due to the uncertainties in the basic nuclear data (ND) is a critical issue. Different error propagation techniques (adjoint/forward sensitivity analysis procedures and/or Monte Carlo technique) can be used to address by computational simulation the systematic propagation of uncertainties on the final parameters. To perform this uncertainty assessment, the ENDF covariance files (variance/correlation in energy and cross-reactions-isotopes correlations) are required.In this paper, we assess the impact of ND uncertainties on the isotopic prediction for a conceptual design of a modular European Facility for Industrial Transmutation (EFIT) for a discharge burnup of 150 GWd/tHM. The complete set of uncertainty data for cross sections (EAF2007/UN, SCALE6.0/COVA-44G), radioactive decay and fission yield data (JEFF-3.1.1) are processed and used in ACAB code.