“…Another advantage of this method as compared to the nuclear reactor neutron-source techniques is a minimum of scattering and thermalizing material present in the vicinity of the sample. The total delayed-neutron yield was measured from the fission of 232 Th, 233 U, 235 U, 238 U, and 239 Pu [217] nuclides. Later, Krick and Evans [218], using the same methodology, measured the total delayed-neutron yield as a function of the neutron energy from the fission of 233 U, 235 U, 238 U, 239 Pu, and 242 Pu in the energy range 0.1 -6.5 MeV.…”