This application discloses a method and an apparatus for processing a nuclear energy spectrum. The apparatus includes: a detector, a nuclear pulse processing module, and a nuclear energy spectrum processing module; the detector is configured to detect nuclear radiation and convert the nuclear radiation into nuclear pulse signals with corresponding amplitudes; the nuclear pulse processing module is configured to shape the nuclear pulse signals into narrow pulses, and perform amplitude analysis on the narrow pulses to generate the nuclear energy spectrum; the nuclear energy spectrum processing module is configured to reduce a value of an energy resolution of the nuclear energy spectrum to obtain the nuclear energy spectrum with the energy resolution of the reduced value.

A gamma-ray spectrometer calibration system comprises a light guide, a photomultiplier tube, a laser, and analysis electronics. The light guide is optically coupled to the scintillation crystal, the laser and the photomultiplier tube, such that the laser can provide reference signals to the photomultiplier tube. In some embodiments, one or more temperature sensors are provided, such that the analysis electronics determine initial settings and adjust the initial settings based on the temperatures measured by the temperature sensors. Additional apparatus, methods, and systems are disclosed.

A method and system to identify an isotope provided in a medium to be characterized by an instrumentation system. The identification method includes: measuring at least one reference spectrum for at least two reference isotopes; defining measurement windows for each reference isotope; measuring a measured spectrum on the medium to be characterized; for each reference isotope, calculating for each of the measurement windows a deviation value representing the deviation between the measured spectrum and that of the reference isotope in the measurement window; for each reference isotope, determining from the calculated deviation values a dissimilarity coefficient; and identifying the isotope from the determined dissimilarity coefficients.

This application discloses a method and an apparatus for processing a nuclear energy spectrum. The apparatus includes: a detector, a nuclear pulse processing module, and a nuclear energy spectrum processing module; the detector is configured to detect nuclear radiation and convert the nuclear radiation into nuclear pulse signals with corresponding amplitudes; the nuclear pulse processing module is configured to shape the nuclear pulse signals into narrow pulses, and perform amplitude analysis on the narrow pulses to generate the nuclear energy spectrum; the nuclear energy spectrum processing module is configured to reduce a value of an energy resolution of the nuclear energy spectrum to obtain the nuclear energy spectrum with the energy resolution of the reduced value.

The radiation imaging apparatus according to the present invention is a radiation imaging apparatus arranged to detect radiation and receive power in a non-contact manner, the radiation imaging apparatus including a control unit configured to stop at least one of the non-contact power reception of and the non-contact power supply to the radiation imaging apparatus depending on the state of the radiation imaging apparatus.

A hybrid radiation detector is described comprising a first energy discriminating detector element selected to be sensitive to incident radiation of a lower energy range and a second detector element selected to be sensitive to incident radiation of a higher energy rage and a second detector element. In embodiments, a first detector element comprises a semiconductor detector; and a second detector element comprises a scintillator detector. The first detector element may thus be suitable to be more responsive to radiation in a first, lower energy range and/or configured and arranged to collect incident radiation emergent from a target of such energy that the photoelectric effect predominates as an attenuation mode in the target; and the second detector element may thus be suitable to be more responsive to radiation in a second, higher energy range and/or configured and arranged to collect incident radiation of a generally higher energy. A method of detecting radiation using such a hybrid detector is also described.

An arrangement for determining an energy spectrum of a beam of radiation or particles is disclosed. The arrangement comprises a plurality of polymeric bodies. Each of the plurality of polymeric bodies includes an optical waveguide. Each of the plurality of polymeric bodies has a scintillator disposed at a respective end of the optical waveguide. The scintillators are arranged relative to each other such that an energy resolution of a particle beam incident on the arrangement can be determined. Furthermore, a particle detector with the arrangement and an evaluation unit for reading out the particle detector are disclosed.

A method for assessing the mass concentration of uranium in a sample of uranium-bearing material by gamma spectrometry, includes a) acquiring (200) an energy spectrum of gamma radiation from the sample using a scintillator detector, the energy spectrum (100) comprising at least a first energy band (110) between 87 keV and 110 keV, and a second energy band (120) between 560 keV and 660 keV, the second energy band comprising at least one energy line (130) at 609 keV from .sup.214Bi, b) calculating (210) an initial mass concentration of uranium (Cm.sub.U0) using the energy spectrum, c) measuring (220) a parameter representative of the height of the sample and a parameter representative of the density of the sample, d) calculating (230) a corrective coefficient (K), and e) calculating (240) a corrected mass concentration of uranium (Cm.sub.U) using the initial mass concentration of uranium (Cm.sub.U0) and the corrective coefficient (K).

A sensor for spectroscopic measurement of alpha and beta particles includes first and second layers, a photomultiplier, and an analyzer. A first material of the first layer scintillates a first stream of photons for each of the alpha particles. However, the beta particles pass through the first layer. A second material of the second layer scintillates a second stream of photons for each of the beta particles, but passes the first stream of photons for each alpha particle. The photomultiplier amplifies the first and second streams of photons for the alpha and beta particles into an electrical signal. The electrical signal includes a respective pulse for each of the alpha and beta particles. From the electrical signal, the analyzer determines a respective energy of each of the alpha and/or beta particles from a shape of the respective pulse for each of the alpha and beta particles.

A method for assessing the mass concentration of uranium in a sample of uranium-bearing material by gamma spectrometry, includes a) acquiring (200) an energy spectrum of gamma radiation from the sample using a scintillator detector, the energy spectrum (100) comprising at least a first energy band (110) between 87 keV and 110 keV, and a second energy band (120) between 560 keV and 660 keV, the second energy band comprising at least one energy line (130) at 609 keV from .sup.214Bi, b) calculating (210) an initial mass concentration of uranium (Cm.sub.U0) using the energy spectrum, c) measuring (220) a parameter representative of the height of the sample and a parameter representative of the density of the sample, d) calculating (230) a corrective coefficient (K), and e) calculating (240) a corrected mass concentration of uranium (Cm.sub.U) using the initial mass concentration of uranium (Cm.sub.U0) and the corrective coefficient (K).