We have discovered an error in our data analysis that affects the result presented in our recent Letter. The evaporation residue cross sections were calculated using the residue yield and the integrated beam. Because elements of the data array used to store the integrated beam did not have sufficient range (maximum 2 16 ), an overflow caused the integrated beam to be counted incorrectly. This was discovered by repeating some of the measurements and checked by reanalyzing the previous data with an appropriately sized data array, and using the originally sized data array but breaking up the analysis into smaller subsets. The correct cross section is presented here in Fig. 1 which replaces Fig. 2 of the original Letter. The size of the correction increases as the beam energy decreases because measurements at lower energies take longer times. At the lowest energy, the corrected cross section is a factor of 4 less than the previously published value. Since a thick target was used, the effective reaction energy was deduced by taking a cross-section-weighted average over the range of the energy loss in the target. The corrected excitation function has a steeper slope at lower energies; therefore, the calculated effective reaction energy is shifted to higher values. Fusion is still enhanced in 132 Sn on 64 Ni at sub-barrier energies with respect to a one-dimensional barrier penetration model prediction. The enhancement of fusion relative to lighter Sn isotopes is no larger than would be expected due to the larger nuclear radius of 132 Sn and transfer does not appear to play a major role in the sub-barrier fusion for this system.[1] W. S. Freeman et al., Phys. Rev. Lett. 50, 1563 (1983.[2] R. Bass, Nucl. Phys. A231, 45 (1974). FIG. 1 (color online). Fusion-evaporation excitation functions of 132 Sn 64 Ni and 64 Ni on even 112-124 Sn [1]. The reaction energy is scaled by the fusion barrier predicted by the Bass model [2] and the evaporation residue (ER) cross section is scaled by the size of the reactants using R 1:2A 1=3 p A 1=3 t , where A p (A t ) is the mass of the projectile (target). The filled circles are corrected data and the open circle is our measurement using a 124 Sn beam.

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The reaction cross-sections of 124Xe(n, 2n)123Xe, 126Xe(n, 2n)125Xe, 128Xe(n, 2n)127Xe, 130Xe(n, 2n)129mXe, 132Xe(n, 2n)131mXe, 130Xe(n, p)130I, 131Xe(n, p)131I, and 132Xe(n, p)132I were measured at the 13.5, 13.8, 14.1, 14.4, and 14.8 MeV neutron energies. The monoenergetic neutrons were generated through the 3H(d,n)4He reaction at the China Academy of Engineering Physics using the K-400 Neutron Generator with a solid 3H-Ti target. A high-purity germanium detector was used to measure the activities of the product. The reactions 93Nb(n, 2n)92mNb and 27Al(n, α)24Na served for neutron flux calibration. The cross sections of the (n,2n) and (n,p) reactions of the xenon isotopes were acquired within the 13–15 MeV neutron energy range. These cross-sections were then compared with the IAEA-exchange format (EXFOR) database-derived experimental data together with the evaluation results of the CENDL-3, ENDF/B-VIII.0, JENDL-4.0, RUSFOND, and JEFF-3.3 data libraries as well as the theoretical excitation function obtained using the TALYS-1.95 code. The cross-sections of the reactions (except for the 124Xe(n, 2n)123Xe and 132Xe(n, p)132I) at 13.5, 13.8, and 14.1 MeV are reported for the first time in this work. The present results are helpful to provide better cross-section constraints for these reactions in the 13–15 MeV region, thus improving the quality of the corresponding database. Meanwhile, these data can also be used for the verification of relevant nuclear reaction model parameters.

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