Assessment of the 153Eu and 154Eu neutron capture cross sections from the integral data assimilation of used nuclear fuel experiments

Feedback from experimental isotopic compositions of used nuclear fuels on neutron cross sections and cumulative fission yields of the JEFF-3.1.1 library by using integral data assimilation

“…153 Eu(n,g) +5.1 ± 2.4% Resonance parameters from reference [31] Resonance parameters extracted from RPI data are in agreement with our study. Possible improvements were already addressed in a previous study [9]. 103 Rh(n,g) +7.4 ± 4.7% Resonance parameters from reference [35] New resonance analysis, performed at IRSN Fontenay aux Roses, suggests an increase of +11% of the capture resonance integral, which is consistent with our results.…”

“…Results are listed by ascending order of adjustment coefficient. In particular, those obtained for the europium capture cross sections and cumulative fission yield of 137 Cs confirm the results previously reported in references [8,9]. Table 4 also compares the relative uncertainties obtained before and after the marginalization of the nuisance parameters (Sect.…”

“…The objectives of the present study are to include most of these C/E-1 ratios in the Integral Data Assimilation procedure of the CONRAD code [5,6] and to provide valuable trends on the nuclear data compiled in the JEFF-3.1.1 library. Guidelines to achieve these objectives and strategies to take into account uncertainties coming from experiments, nuclear data and numerical biases are discussed in references [7][8][9]. The originality of our approach lies in the use of the AGS code method [10] to generate covariances between the C/E-1 ratios and of the marginalization procedure [11] to propagate uncertainties of "nuisance" parameters.…”