The present invention relates to a radiation detector (100) comprising: i) a substrate (110); ii) a sensor, which is coupled to the substrate, the sensor comprising a first array (120) of sensor pixels, a second array (130) of signal read-out elements, and an electronic circuitry which is configured to provide image data based on signals received from the signal read-out elements; iii) a transducer, which is coupled to the substrate and to the sensor, the transducer comprising a third array (140) of subpixels, wherein at least two subpixels are assigned to one sensor pixel; wherein the second array of signal read-out elements and the third array of subpixels correspond to each other; wherein each of the subpixels comprises a radiation conversion material.

The present invention relates to a radiation detector (100) comprising: i) a substrate (110); ii) a sensor, which is coupled to the substrate, the sensor comprising a first array (120) of sensor pixels, a second array (130) of signal read-out elements, and an electronic circuitry which is configured to provide image data based on signals received from the signal read-out elements; iii) a transducer, which is coupled to the substrate and to the sensor, the transducer comprising a third array (140) of subpixels, wherein at least two subpixels are assigned to one sensor pixel; wherein the second array of signal read-out elements and the third array of subpixels correspond to each other; wherein each of the subpixels comprises a radiation conversion material.

The present invention relates to a method for the quantification of radionuclides in liquid media comprising measuring a gamma-ray spectrum, a device for the quantification of radionuclides in liquid media and the use for the quantification of radionuclide concentrations in hydrometallurgical processing media, especially the quantification of uranium and/or radioactive uranium decay product concentrations in uranium mining solutions or in uranium recovery solutions or the quantification of thorium and/or radioactive .sup.232Th decay products in rare-earth element processing solutions.

The present invention relates to a method for the quantification of radionuclides in liquid media comprising measuring a gamma-ray spectrum, a device for the quantification of radionuclides in liquid media and the use for the quantification of radionuclide concentrations in hydrometallurgical processing media, especially the quantification of uranium and/or radioactive uranium decay product concentrations in uranium mining solutions or in uranium recovery solutions or the quantification of thorium and/or radioactive .sup.232Th decay products in rare-earth element processing solutions.

A method for generating a response function of a scintillator to incident gamma rays of energy within a range of energies of interest, the method including: obtaining the responses {S.sub.i} of the scintillator to a plurality of known radionuclides i (i=1, . . . N), each radionuclide i emitting gamma rays with known energetic properties (E.sub.ij, Y.sub.ij), decomposing, for each radionuclide i, response S.sub.i into primary responses of the scintillator S.sub.ij=ƒ(λ.sub.ij, Y.sub.ij, X.sub.ij), each primary response corresponding to the response of the scintillator to a received gamma ray of a known energy E.sub.ij for this radionuclide i, deriving from the primary responses {S.sub.ij} the response function ƒ(λ, X) of the scintillator to an incident gamma ray of any energy E within the range of energies of interest.

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.

An in-core detector configured to measure a power distribution in a nuclear reactor is disclosed herein. The in-core detector includes a housing configured to be placed within a predetermined location of the nuclear reactor and a plurality of a gamma detectors. Each gamma detector of the plurality of gamma detectors includes a Schottky diode including an active semiconductor region and a Schottky contact, an Ohmic contact, a photoelectron source material configured to transfer electrons to the active region upon contact with gamma radiation, and a first and second lead. The plurality of gamma detectors are positioned within the housing such that each gamma detector of the plurality of gamma detectors is radially offset relative to an adjacent gamma detector of the plurality of gamma detectors, such that the first and second leads of each gamma detector are offset relative to the first and second leads of the adjacent gamma detector.

Systems and methods to estimated mean randoms include acquisition of list mode data describing true coincidences and delay coincidences detected by a positron emission tomography scanner during a scan of an object, determination, for each crystal of the positron emission tomography scanner and for each of a plurality of time periods of the scan, of delay coincidences including the crystal based on the list mode data, determination, each crystal, of determine a singles rate associated with each time period based on the delay coincidences determined for the crystal over the time period, determination, for each time period, of determine estimated mean randoms for each of a plurality of pairs of the crystals based on the singles rate associated with the time period for each crystal of the crystal pair, and reconstruction of an image of the object based on the estimated mean randoms for each time period and the detected true coincidences.

In one embodiment, a surface has a laser-beam machined area including an array of micro-sized conical pillars that are arranged in orthogonal rows and columns across the surface and that extend upward, the conical pillars defining deep troughs between them that are configured to absorb electrons, electromagnetic radiation, or both, the conical pillars tapering from relatively wide bases to pointed tips, the conical pillars comprising outer surfaces that are covered with a plurality of nanoparticles.

In one embodiment, a surface has a laser-beam machined area including an array of micro-sized conical pillars that are arranged in orthogonal rows and columns across the surface and that extend upward, the conical pillars defining deep troughs between them that are configured to absorb electrons, electromagnetic radiation, or both, the conical pillars tapering from relatively wide bases to pointed tips, the conical pillars comprising outer surfaces that are covered with a plurality of nanoparticles.