prompt gamma, 252Cf, HPGe, MCNP, ENDF/B-VIII.0
Cross section measurement, D-T generator, Neutron dosimetry, Sample irradiation
Spectrum-averaged cross sections, 252Cf neutron source, inelastic scattering, tin foil, zinc foil
LR-0 reactor, Graphite shaped neutron field, MCNP, Reaction rate measurement
Neutron leakage spectrum, 252Cf, Al cross section, validation, activation foils
photonuclear reactions, bremsstrahlung, activation detectors, photofission, uranium-238, evaluated nuclear data, gamma-ray spectrometry