Shielding integral experiment of slab Zr samples based on a D-T neutron source

This dataset was obtained from the shielding integral experiment on a pulsed accelerator at China Institute of Atomic Energy. To verify the reliability of the experimental system and data analysis methods, polyethylene was selected as a standard sample for benchmark experimental measurements and corresponding simulation calculations. Since the n–p elastic scattering cross section of hydrogen in polyethylene is internationally recognized as a standard cross section with relatively small nuclear data uncertainties, polyethylene serves as a reference material for validating the experimental system. Leakage neutron time-of-flight spectra were acquired at equivalent angles of 47°, 61°, and 79°, providing a basis for assessing the reliability of the natural zirconium experimental data.