The measurement of the neutron total cross section of natural silver in the resonance region from 10 to 100 eV at CSNS Back-n

This work is based on measurements carried out at the Back-n white neutron facility of the China Spallation Neutron Source (CSNS). The neutron total cross sections of natural silver were measured in the resonance energy range from 10 to 100 eV. In addition, the R-matrix code SAMMY was employed to fit the neutron transmission data, yielding the corresponding resonance parameters.For data processing, neutron energies were determined by the time-of-flight (TOF) method. The neutron transmission rate was measured using the transmission technique, and combined with the sample areal density, the neutron total cross sections were obtained.The datasets provided as attachments are described below:“Neutron Transmission and Total Cross Section Data”Column 1: Neutron energy (eV).Columns 2 and 3: Detector neutron counts within and without the silver sample, respectively.Column 4: Neutron transmission, derived from the transmission formula.Column 5: Neutron total cross section (barns), calculated using the sample areal density.Column 6: Uncertainty of the neutron total cross section, obtained through the error propagation formula. 2“Resonance Parameters of Ag-107 Fitted by SAMMY.” and “Resonance Parameters of Ag-109 Fitted by SAMMY.”These two datasets list the resonance parameters of Ag-107 and Ag-109 obtained in this work, including the neutron resonance energy and neutron resonance width (Columns 1–2). The resonance parameters reported by Xin-Xiang Li (Columns 3–4), as well as the reference values from the evaluated nuclear data libraries ENDF/B-VIII.0 and CENDL-3.2 (Columns 5–8), are also presented.Column 1: Neutron resonance energy (eV) of this work.Column 2: Neutron resonance width(meV) of this work.Column 3: Neutron resonance energy (eV) of Xin-Xiang Li.Column 4: Neutron resonance width(meV) of Xin-Xiang Li.Column 5: Neutron resonance energy (eV) from ENDF/B-VIII.0.Column 6: Neutron resonance width(meV) from ENDF/B-VIII.0.Column 7: Neutron resonance energy (eV) from CENDL 3.2.Column 8: Neutron resonance width(meV) from CENDL 3.2.These datasets provide neutron total cross sections and resonance parameters of natural silver in the 10–100 eV resonance region, enriching the experimental database of natural silver neutron total cross section measurements.