prompt gamma, 252Cf, HPGe, MCNP, ENDF/B-VIII.0
Cross section measurement, D-T generator, Neutron dosimetry, Sample irradiation
Neutron-gamma analyser, P-Terphenyl scintillator, Light output, Pulse-shape discrimination (PSD), Neutron efficiency, Digital-signal processing
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
Deep penetration neutron spectra experiment on chlorine, Collimated neutron beamline, Discrepancies observed between 1.1 MeV and 10 MeV for ENDF, JENDL and JEFF libraries, Serpent2 spectra outliers which might be attributed to nuclear data file formatting issues or an algorithmic problem
BR1 reactor, 235U PFNS, MARK III converter, S84, IRDFF-II, validation
photonuclear reactions, bremsstrahlung, activation detectors, photofission, uranium-238, evaluated nuclear data, gamma-ray spectrometry