Abstract: A single photon radiation detector is designed for a particular radiation source fluence, such that an incident radiation photon strikes a scintillator monolith, creating scintillation photons, which are amplified by appropriately sized channels of photomultipliers optically coupled to the scintillator monolith. The photomultiplier output is electronically shaped into a corresponding stream of scintillation pulses (otherwise referred to as scintillation photons) that pass through a comparator to produce a bitstream of the detected scintillation photons, which is sampled into a field programmable gate array (FPGA) acting as a giga-sample transceiver to produce time-to-digital conversions, capable of producing an output data stream of 10's-of-giga-samples per second or more. Appropriate design ensures sparsity of scintillation photon arrival, so that each photon in the bitstream corresponds to a single incident scintillation photon.

Abstract: A single volume fission energy neutron detector is described herein. The detector includes a single volume of scintillator. A photodetector is positioned adjacent to a surface of the scintillator, wherein the photodetector has relatively small spatial resolution corresponding thereto and relatively small temporal resolution corresponding thereto. Based upon values read out from detection bins of the photodetector, kinematics of a neutron that interacted with scintillating material of the scintillator are reconstructed. Based upon the kinematics (of the neutron and other detected neutrons), a location of material from which the neutron was emitted is ascertained, and an image of the material is generated.

Abstract: The various technologies presented herein relate to detecting nuclear material at a large stand-off distance. An imaging system is presented which can detect nuclear material by utilizing time encoded imaging relating to maximum and minimum radiation particle counts rates. The imaging system is integrated with a data acquisition system that can utilize variations in photon pulse shape to discriminate between neutron and gamma-ray interactions. Modulation in the detected neutron count rates as a function of the angular orientation of the detector due to attenuation of neighboring detectors is utilized to reconstruct the neutron source distribution over 360 degrees around the imaging system. Neutrons (e.g.