The characterization of a newly developed capture-gated neutron spectrometer is presented. Such spectrometers produce a dual signal from incoming neutrons, allowing for differentiation between other particles, particularly gamma rays. The neutron provides a primary light pulse in either plastic or liquid scintillator through neutron-proton collisions. A capture material then captures the moderated neutron exciting the material. The capture material promptly de-excites with the emission of gamma rays, which then produces a second pulse. The present spectrometer alternates one-centimeter thick plastic scintillators with sheets of cadmium inserted in between for neutron capture. Each neutron captured in cadmium releases about 9 MeV of gamma energy. Many factors influence the operation of the spectrometer, including: materials, geometry, optics, and methods of analysis. Experiments are presented that weigh the effect that these factors have on the capabilities of the detector. Theoretical, computational and experimental data presented here also illustrates the detector's ability to be utilized in applications of neutron detection for nuclear non-proliferation. The intrinsic efficiency of the detector for the detection of spontaneous fission neutrons from Cf-252 is measured to be 5.23%.