The159Tb neutron capture yield from 1eV to 1.2keV

This dataset is Figure 2 from the article "Resonance parameters of 159Tb neutron capture cross section within 100eV" published in 《Nuclear Science and Techniques》. This dataset contains mainly experimental data obtained in the energy range of 1eV to 1.2keV. This dataset contains mainly experimental data obtained from resonance analyses of reactions using the R matrix code SAMMY in the 1eV to 1.2keV energy range. As well as the resonance parameters of the neutron capture reaction in the range of 1eV to 100eV, such as resonance energy (Er), resonance spin (J), radiation width (Γγ), neutron width (Γn), and so on. The experiments corresponding to this dataset were carried out at the China Scattered Neutron Source (CSNS) at the Back-angled White-Light Neutron Beamline (Back-n) facility, where the neutron-capture cross section was measured using the C6D6 detector array. A pure terbium metal sample with a diameter of 30.0 mm and a thickness of 0.2 mm was used for the instantaneous capture γ-ray measurements, while natural lead (natPb) and Au samples and empty sample holders were used for the background evaluation and normalisation, and samples of 59Co and 181Ta were used as absorber slices. The analysis of the experimental data relies heavily on Monte Carlo simulations using the Geant4 toolkit and efficiency corrections using the pulse height weighting technique (PHWT). Resonance parameters are obtained by fitting the measured capture yields to the R matrix code SAMMY based on the Reich-Moore approximation, taking into account the experimental conditions, neutron multiple scattering, self-shielding and the Doppler effect. These data can be used in the fields of validation of nuclear models, study of nucleosynthesis during neutron capture, and applications of nuclear technology, providing an important experimental basis for related research. For example, the analysis of resonance parameters provides insight into the structure and properties of atomic nuclei and the mechanism of neutron-nucleus interaction. At the same time, these data can also provide reference for nuclear data evaluation and nuclear technology applications, such as the calculation of Maxwell average cross section (MACS).