A gamma-ray spectrum classification apparatus, comprising circuitry configured: to provide a denoising autoencoder to receive gamma-ray spectrum data representing a gamma-ray spectrum of a material to be classified and to determine feature data indicative of one or more features representative of the gamma-ray spectrum data; and to provide a classification neural network to receive the feature data and to classify the material to be classified as one of a plurality of predetermined classifications using the feature data.

Eutectic lithium chloride-cerium chloride (LiCl—CeCl.sub.3) compositions are described. An exemplary eutectic composition has about 75 mole % LiCl and about 25 mole % CeCl.sub.3. The eutectic compositions can have optical and/or scintillation properties. Also described are methods of preparing the eutectic compositions as well as methods of using radiation detectors including the eutectic compositions in the detection of radiation, including thermal neutrons.

A spectroscopic gamma and neutron detecting device includes a scintillation detector that detects gamma and thermal neutron radiation, the scintillation detector including signal detection and amplification electronics, and a stabilization module configured to measure a pulse height spectrum of neutron radiation, determine a thermal neutron peak position in the neutron pulse height spectrum originating from cosmic ray background radiation, monitor the thermal neutron peak position in the neutron pulse height spectrum during operation of the spectroscopic gamma and neutron detecting device, and adjust the signal detection and amplification electronics based on the thermal neutron peak position in the neutron pulse height spectrum, thereby stabilizing the spectroscopic gamma and neutron detecting device.

A method of measurement of both gamma radiation and neutrons with energies above 500 keV is provided utilizing a scintillation crystal. The method includes allowing gamma quanta and neutrons to interact with the scintillation crystal, collecting light emitted by the scintillation crystal and letting that light interact with a photo detector, and amplifying the signal output. The method then digitizes the amplifier output signal, determines a charge collection time for each interaction measured, determining light decay times, separating signals with distinct decay times, determining a total charge collected from signals with the distinct decay times, and sorting charge signals in a spectrum. The method then counts signals with a second decay time and determines a count rate.

Techniques are disclosed for systems and methods to provide a radiation detector module for a radiation detector. A radiation detector module includes a metallic and/or metalized enclosure, a radiation sensor disposed within the enclosure, readout electronics configured to provide radiation detection event signals corresponding to incident ionizing radiation in the radiation sensor, and a cap including an internal interface configured to couple to the readout electronics and an external interface configured to couple to a radiation detector, where the cap is configured to hermetically seal the radiation sensor within the enclosure. The cap may be implemented as an edge plated printed circuit board (PCB) including a slot configured to mate with a planar edge of an open surface of the enclosure, where the slot is soldered to the planar edge of the enclosure to hermetically seal the radiation sensor within the enclosure.

A spectroscopic gamma and neutron detecting device includes a scintillation detector that detects gamma and thermal neutron radiation, the scintillation detector including signal detection and amplification electronics, and a stabilization module configured to measure a pulse height spectrum of neutron radiation, determine a thermal neutron peak position in the neutron pulse height spectrum originating from cosmic ray background radiation, monitor the thermal neutron peak position in the neutron pulse height spectrum during operation of the spectroscopic gamma and neutron detecting device, and adjust the signal detection and amplification electronics based on the thermal neutron peak position in the neutron pulse height spectrum, thereby stabilizing the spectroscopic gamma and neutron detecting device.

A neutron spectrum generator is disclosed herein including a neutron source, a scatterer positioned in a direct path between the neutron source and a neutron detector, and a material shell configured to have at least one non-uniform characteristic selected from the group consisting of a material, a thickness, a length, an angle, a layer, and combinations thereof to generate a specific spectrum at the neutron detector that is different than the spectrum of the neutron source. A related method includes measuring a first response generated by a first material shell of a neutron spectrum generator interacting with a neutron source, replacing the first material shell with a second material shell, measuring a second response generated by a second material shell of a neutron spectrum generator interacting with the neutron source, and determining a total fission response by determining a difference between the first response and the second response.

Eutectic lithium chloride-cerium chloride (LiCl—CeCl.sub.3) compositions are described. An exemplary eutectic composition has about 75 mole % LiCl and about 25 mole % CeCl.sub.3. The eutectic compositions can have optical and/or scintillation properties. Also described are methods of preparing the eutectic compositions as well as methods of using radiation detectors including the eutectic compositions in the detection of radiation, including thermal neutrons.

Techniques are disclosed for systems and methods to provide a radiation detector module for a radiation detector. A radiation detector module includes a metallic and/or metalized enclosure, a radiation sensor disposed within the enclosure, readout electronics configured to provide radiation detection event signals corresponding to incident ionizing radiation in the radiation sensor, and a cap including an internal interface configured to couple to the readout electronics and an external interface configured to couple to a radiation detector, where the cap is configured to hermetically seal the radiation sensor within the enclosure. The cap may be implemented as an edge plated printed circuit board (PCB) including a slot configured to mate with a planar edge of an open surface of the enclosure, where the slot is soldered to the planar edge of the enclosure to hermetically seal the radiation sensor within the enclosure.

An inventive neutron detector includes an n-type GaN wafer and a photomultiplier, which are optically coupled with each other. The n-type GaN wafer is irradiated with neutrons from a neutron source, such as including a particle accelerator and a beryllium target. Scintillation of the n-type GaN resulting from the neutron irradiation is amplified by the photomultiplier and is analyzed using a data acquisition system.