Neutron capture cross-section measurement and extraction of neutron resonance parameters at 1–500 eV for 109Ag

This work conducted neutron capture cross-section experiments on 109Ag isotope targets using a white light neutron source from the Chinese Spallation Neutron Source. By combining neutron flight time method and pulse height weighting technique, the neutron capture cross-section of 109Ag in the energy range of 1-500 eV was obtained. The resonance energy, neutron resonance width, and gamma resonance width parameters of 109Ag were extracted using the SAMMY program based on the R-matrix theory. This dataset includes a flowchart for obtaining resonance parameters, namely the graph methodology, as shown in Figure 2 of this article; The normalized counting table is the data obtained by normalizing the pulse height spectra of each target using a Li Si detector, as shown in Figures 4 and 5 of this article; Table detection efficiency refers to the detector detection efficiency before and after weighted counting using pulse height, as shown in Figure 6 of this article; Table fc shows the relationship between the simulated neutron to target thickness ratio and neutron energy variation, as shown in Figure 7 of this article; Table 109Ag cross-sectional data refers to the neutron capture cross-sectional data obtained experimentally, which is the data for This Work in Figure 8 of this article; The table resonance parameters refer to the 109Ag resonance parameter data extracted from the SAMMY program, which is the data for This Work in Table 3 of this article.