A detection element includes an exposed electrode on the first surface of an insulating substrate, the exposed electrode including first exposed electrode, second exposed electrode, third exposed electrode, and fourth exposed electrode provided; a first electrode pattern provided on a side opposite to the first surface, the first electrode pattern including a pattern connected to the first exposed electrode and the second exposed electrode, a pattern connected to the third exposed electrode and the fourth exposed electrode, a second electrode pattern having a first exposed portion and a pattern provided along the second direction, and a third electrode pattern having a second exposed portion and a pattern provided along the third direction, provided so as to sandwich the third electrode pattern between the first electrode pattern and the second electrode pattern.

A detection element includes an exposed electrode on the first surface of an insulating substrate, the exposed electrode including first exposed electrode, second exposed electrode, third exposed electrode, and fourth exposed electrode provided; a first electrode pattern provided on a side opposite to the first surface, the first electrode pattern including a pattern connected to the first exposed electrode and the second exposed electrode, a pattern connected to the third exposed electrode and the fourth exposed electrode, a second electrode pattern having a first exposed portion and a pattern provided along the second direction, and a third electrode pattern having a second exposed portion and a pattern provided along the third direction, provided so as to sandwich the third electrode pattern between the first electrode pattern and the second electrode pattern.

A method for determining a radionuclide concentration of a material is provided. The method comprises placing a detector in a protective structure, wherein the detector is coupled to a single-channel analyzer. The method further comprises inserting the protective structure in a material, wherein the material comprises a radionuclide. The method additionally comprises measuring the moisture content of the material to be analyzed. The method also comprises counting the emitted radiation having a known energy over an interval of time to produce a count per time, wherein the emitted radiation is emitted from the radionuclide and then dividing the count per time by the weight of the material to produce a count per time per weight.

A method for determining a radionuclide concentration of a material is provided. The method comprises placing a detector in a protective structure, wherein the detector is coupled to a single-channel analyzer. The method further comprises inserting the protective structure in a material, wherein the material comprises a radionuclide. The method additionally comprises measuring the moisture content of the material to be analyzed. The method also comprises counting the emitted radiation having a known energy over an interval of time to produce a count per time, wherein the emitted radiation is emitted from the radionuclide and then dividing the count per time by the weight of the material to produce a count per time per weight.

A neural network based corrector for photon counting detectors is described. A method for photon count correction includes receiving, by a trained artificial neural network (ANN), a detected photon count from a photon counting detector. The detected photon count corresponds to an attenuated energy spectrum. The attenuated energy spectrum is related to characteristics of an imaging object and is based, at least in part, on an incident energy spectrum. The method further includes correcting, by the trained ANN, the detected photon count to produce a corrected photon count. The method may include reconstructing, by image reconstruction circuitry, an image based, at least in part, on the corrected photon count.

A neural network based corrector for photon counting detectors is described. A method for photon count correction includes receiving, by a trained artificial neural network (ANN), a detected photon count from a photon counting detector. The detected photon count corresponds to an attenuated energy spectrum. The attenuated energy spectrum is related to characteristics of an imaging object and is based, at least in part, on an incident energy spectrum. The method further includes correcting, by the trained ANN, the detected photon count to produce a corrected photon count. The method may include reconstructing, by image reconstruction circuitry, an image based, at least in part, on the corrected photon count.

Disclosed is a directional gamma ray or neutron detector system that locates a radioactive source both horizontally and vertically. In some embodiments, the system comprises four side detectors arrayed around a detector axis, and an orthogonal front detector mounted frontward of the side detectors. Embodiments can calculate the azimuthal angle of the source based on the detection rates of the side detectors, while the polar angle of the source may be calculated from the front detector rate using a predetermined angular correlation function, thereby localizing the source from a single data set without iterative rotations. In applications such as hand-held survey meters, walk-through portals, vehicle cargo inspection stations, and mobile area scanners, embodiments enable rapid detection and precise localization of clandestine nuclear and radiological weapons.

A radiation detector includes a plurality of pixels configured to detect radiation, and at least one of the plurality of pixels includes a radiation absorbing layer configured to convert photons incident on the radiation absorbing layer into a first electrical signal, and a photon processor including a plurality of storages configured to count and store the number of the photons based on the first electrical signal. At least one of the plurality of storages is configured to compare the first electrical signal with a first reference value to obtain a second electrical signal, and count and store the number of the photons based on a third electrical signal that is obtained based on a comparison of the second electrical signal with a second reference value.

A radiation detector includes a plurality of pixels configured to detect radiation, and at least one of the plurality of pixels includes a radiation absorbing layer configured to convert photons incident on the radiation absorbing layer into a first electrical signal, and a photon processor including a plurality of storages configured to count and store the number of the photons based on the first electrical signal. At least one of the plurality of storages is configured to compare the first electrical signal with a first reference value to obtain a second electrical signal, and count and store the number of the photons based on a third electrical signal that is obtained based on a comparison of the second electrical signal with a second reference value.

Techniques are disclosed for systems and methods to detect radiation accurately, and particularly in a highly radioactive environment. A system includes a detector module for a radiation detector and a parallel signal analyzer configured to receive radiation detection event signals from the detector module and provide a spectroscopy output and a dose rate output. The parallel signal analyzer may be configured to analyze the radiation detection event signals in parallel in first and second analysis channels according to respective first and second measurement times and determine the spectroscopy output and the dose rate output based on radiation detection event energies determined according to the respective first and second measurement times.