A dosimeter for characterising a spatial distribution of a radiation dose in a sensing region, the dosimeter comprising; a plurality of scintillation fibres extending substantially parallel to a first direction in the sensing region and arranged in a two-dimensional array in a plane perpendicular to the first direction, wherein the radiation absorption properties of the plurality of scintillation fibres are configured to approximate the radiation absorption properties of human body tissue; and a photodetector comprising a plurality of photodetector regions coupled to respective ones of the plurality of scintillation fibres so as to generate signals for respective ones of the photodetector regions in response to radiation interaction events in corresponding ones of the scintillation fibres; further comprising a controller arranged to receive the signals from the photodetector regions and to determine a spatial distribution of a radiation dose in the sensing region.
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
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Downloadable and recorded software for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation; hardware for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation; radiation measuring instruments; radiation detectors; equipment and apparatus for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation Scientific research and design related thereto in the field of nuclear detection, nuclear identification and nuclear security; calibration of radiation detection and measurement instruments; providing temporary use of online, non-downloadable software for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation; technological consulting services in the field of nuclear detection, nuclear identification and nuclear security.
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
Software and hardware for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation; radiation measuring instruments; radiation detectors; equipment and apparatus for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation. Scientific and technological services and research and design related thereto; calibration of radiation detection and measurement instruments.
A dosimeter for characterising a spatial distribution of a radiation dose in a sensing region, the dosimeter comprising; a plurality of scintillation fibres extending substantially parallel to a first direction in the sensing region and arranged in a two-dimensional array in a plane perpendicular to the first direction, wherein the radiation absorption properties of the plurality of scintillation fibres are configured to approximate the radiation absorption properties of human body tissue; and a photodetector comprising a plurality of photodetector regions coupled to respective ones of the plurality of scintillation fibres so as to generate signals for respective ones of the photodetector regions in response to radiation interaction events in corresponding ones of the scintillation fibres; further comprising a controller arranged to receive the signals from the photodetector regions and to determine a spatial distribution of a radiation dose in the sensing region based on the extent to which the signals from the plurality of photodetector regions indicate there have been radiation interaction events in different ones of the plurality of scintillation fibres.
A nuclear radiation monitoring apparatus comprising: communication circuitry configured to receive nuclear radiation data generated by a nuclear radiation detector, the nuclear radiation data being indicative of nuclear radiation emitted from each of a plurality of portions of an object and detected by the nuclear radiation detector; classification circuitry configured to classify the detected nuclear radiation using the nuclear radiation data; intensity determination circuitry configured to determine a value of an intensity parameter indicative of an intensity of the classified nuclear radiation for each portion of the object using the nuclear radiation data; visualisation data generation circuitry configured to generate visualisation data indicative of the classification of the classified nuclear radiation and, for each portion of the object, visualisation data indicative of the portion of the object and the determined intensity parameter value of the portion of the object; and display output circuitry configured to output the generated visualisation data for display.
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.
An apparatus comprises a neutron detector. The neutron detector comprises a conversion layer comprising a mixture of a neutron absorbing material and a scintillation material; and a photodetector optically coupled to the conversion layer and arranged to detect photons generated as a result of neutron absorption events in the conversion layer; wherein the apparatus is adapted to be carried by a user and the conversion layer is positioned within the neutron detector such that when the apparatus is being carried by a user in normal use neutrons are absorbed in the conversion layer after passing through the user such that the user's body provides a neutron moderating effect. In some cases the apparatus may be carried in association with a backpack or clothing worn by a user, for example, the neutron detector may be sized to fit in a pocket. In other cases the apparatus may be a hand-held device with the conversion layer arranged within a handle of the device to be gripped by a user when being carried.
G01T 3/08 - Measuring neutron radiation with semiconductor detectors
G01T 3/06 - Measuring neutron radiation with scintillation detectors
G01N 23/09 - Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups , or by transmitting the radiation through the material and measuring the absorption the radiation being neutrons
G01T 1/20 - Measuring radiation intensity with scintillation detectors
A gamma ray detector is described. The detector comprises a plastic scintillation body for receiving gamma rays and generating photons in response thereto. The scintillation body is in the form of a truncated cone defined by a base surface and an end surface separated along an axis of extent of the scintillation body with a lateral surface extending therebetween. A photodetector is optically coupled to the base surface of the scintillation body so as to detect photons generated by gamma ray interaction events within the scintillation body. A specular reflector is provided adjacent, but separated from, the lateral surface of the scintillation body so as to reflect photons that leave the scintillation body through the lateral surface back into the scintillation body.
A gamma-ray detector for determining the direction to a source of gamma-rays is described. The detector comprises a first scintillation body coupled to a first photodetector and a second scintillation body coupled to a second photodetector, wherein the first scintillation body and the second scintillation body are arranged to be co-axial with a pointing axis of the detector. The detector further comprises a processing circuit arranged to receive output signals associated with the first and second photodetectors for a plurality of different orientations of the pointing axis of the detector relative to a reference direction. The processing circuit is further operable to determine a direction to the source of gamma-rays relative to the reference direction based on output signals associated with the first and second photodetectors for the plurality of different orientations of the pointing axis of the detector relative to the reference direction.
A neutron detector comprises one or more neutron detector modules (20). Each neutron detector module (20) comprises a neutron moderating block (22) having a plurality of neutron detector blades (2) embedded therein. Each neutron detector blade (2) is generally planar and comprises conversion layers on either side of a light-guiding sheet (8). Each conversion layer (4a, 4b) comprises a mixture of a neutron absorbing material and a scintillation material. This light-guiding sheet (8) is arranged to receive photons emitted from the scintillation material. A photodetector (10) is optically coupled to the light-guide (8) and arranged to detect photons generated in the conversion layers (4a, 4b) as a result of neutron absorption events and received into the light-guiding sheet (8).
A calibration source for a gamma-ray spectrometer is provided, comprising a scintillator body having a cavity in which a radioactive material is received. A scintillator body may be cuboid and the cavity may be a hole drilled into the scintillator body. The radioactive material comprises an isotope having a decay transition associated with emission of a radiation particle and a gamma-ray of known energy. A photodetector is optically coupled to the scintillator body and arranged to detect scintillation photons generated when radiation particles emitted from the radioactive material interact with the surrounding scintillator. A gating circuit is arranged to receive detection signals to generate corresponding gating signals for a data acquisition circuit of an associated gamma-ray spectrometer to indicate that gamma-ray detections in the gamma-ray spectrometer occurring within a time window defined by the gating signal are associated with a decay transition in the radioactive isotope.
An apparatus is described. The apparatus comprising a gamma-ray spectrometer arranged to receive gamma-rays from a calibration source, the gamma-ray spectrometer comprising: a scintillator material optically coupled to two or more photomultipliers, the two or more photomultipliers being arranged to detect photons generated in the scintillator material associated with gamma-ray interactions between the scintillator material and gamma-rays received from the calibration source, wherein the two or more photomultipliers are operable to output respective detection signals associated with the gamma-ray interactions; the apparatus further comprising: a switch coupled to receive the respective detection signals from the two or more photomultipliers and operable to select detection signals from one of the two or more photomultipliers; and a stabilization circuit coupled to the switch and operable to receive the selected detection signal of the respective photomultiplier and to stabilize the gain of the photomultiplier that output the selected detection signal based on the detection signals.
A gamma ray detector is described. The detector comprises a plastic scintillation body for receiving gamma rays and generating photons in response thereto. The scintillation body is in the form of a truncated cone defined by a base surface and an end surface separated along an axis of extent of the scintillation body with a lateral surface extending therebetween. A photodetector is optically coupled to the base surface of the scintillation body so as to detect photons generated by gamma ray interaction events within the scintillation body. A specular reflector is provided adjacent, but separated from, the lateral surface of the scintillation body so as to reflect photons that leave the scintillation body through the lateral surface back into the scintillation body.
A gamma-ray detector for determining the direction to a source of gamma-rays is described. The detector comprises a first scintillation body coupled to a first photodetector and a second scintillation body coupled to a second photodetector, wherein the first scintillation body and the second scintillation body are arranged to be co-axial with a pointing axis of the detector. The detector further comprises a processing circuit arranged to receive output signals associated with the first and second photodetectors for a plurality of different orientations of the pointing axis of the detector relative to a reference direction. The processing circuit is further operable to determine a direction to the source of gamma-rays relative to the reference direction based on output signals associated with the first and second photodetectors for the plurality of different orientations of the pointing axis of the detector relative to the reference direction.
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
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Software and hardware for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation; radiation measuring instruments; radiation detectors; equipment and apparatus for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation Scientific and technological services, namely, research and design in the field of identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation; calibration of radiation detection and measurement instruments
A neutron spectrometer is described. The neutron detector comprises a conversion layer provided on an outer surface of a spherical core of neutron-moderating material. The conversion layer comprises a neutron absorbing material and a phosphor material. The spherical core is arranged to receive photons emitted from the phosphor material of the conversion layer. The neutron detector further comprises a photodetector optically coupled to the spherical core and arranged to detect the photons emitted from the conversion layer.
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
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Software and hardware for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation; radiation measuring instruments; radiation detectors; equipment and apparatus for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation. Scientific and technological services and research and design related thereto; calibration of radiation detection and measurement instruments.
An apparatus is described. The apparatus comprising a gamma-ray spectrometer arranged to receive gamma-rays from a calibration source, the gamma-ray spectrometer comprising: a scintillator material optically coupled to two or more photomultipliers, the two or more photomultipliers being arranged to detect photons generated in the scintillator material associated with gamma-ray interactions between the scintillator material and gamma-rays received from the calibration source, wherein the two or more photomultipliers are operable to output respective detection signals associated with the gamma-ray interactions; the apparatus further comprising: a switch coupled to receive the respective detection signals from the two or more photomultipliers and operable to select detection signals from one of the two or more photomultipliers; and a stabilization circuit coupled to the switch and operable to receive the selected detection signal of the respective photomultiplier and to stabilize the gain of the photomultiplier that output the selected detection signal based on the detection signals.
A calibration source for a gamma-ray spectrometer is provided. The calibration source comprises a scintillator body having a cavity in which a radioactive material is received. The scintillator body may be generally cuboid and the cavity may be formed by a hole drilled into the scintillator body. The radioactive material comprises a radioactive isotope having a decay transition associated with emission of a radiation particle and a gamma-ray having a known energy e.g.Na-22. A photodetector, for example a silicon photomultiplier, is optically coupled to the scintillator body and arranged to detect scintillation photons generated when radiation particles emitted from the radioactive material interact with the surrounding scintillator bod. A gating circuit is arranged to receive detection signals from the photodetector and to generate corresponding gating signals for a data acquisition circuit of an associated gamma-ray spectrometer to indicate that gamma-ray detections in the gamma-ray spectrometer occurring within a time window defined by the gating signal are associated with a decay transition in the radioactive isotope. Thus a calibration source is provided based around a simple scintillator body design. Furthermore, the radioactive material may be introduced into the scintillator body in a separate step after manufacture of the scintillator body, thereby reducing the risk of radioactive contamination during manufacture.
A neutron spectrometer (2) is described. The neutron detector (2) comprises a conversion layer (4) provided on an outer surface of a spherical core (6) of neutron-moderating material. The conversion layer comprises a neutron absorbing material and a phosphor material. The spherical core is arranged to receive photons emitted from the phosphor material of the conversion layer. The neutron detector further comprises a photodetector (10) optically coupled to the spherical core and arranged to detect the photons emitted from the conversion layer. The conversion layer is provided with a diffusely reflective surface orientated toward the centre of the spherical core arranged to diffusely reflect the photons emitted from the conversion layer and wherein the spherical core is arranged to guide the photons to the photodetector.
6Li, and a phosphorescent material, e.g., ZnS(Ag) and a wavelength-shifting light-guide arranged to receive photons emitted from the phosphorescent material and generate wavelength-shifted photons therefrom. The wavelength-shifting light-guide is doped so as to form a gamma-ray scintillator material operable to generate scintillation photons in response to a gamma-ray detection event therein. A photodetector is optically coupled to the wavelength-shifting light-guide and arranged to detect the wavelength-shifted photons and the scintillation photons. Signals from the photodetector are processed to distinguish neutron detection events from gamma-ray detection events.
A neutron spectrometer is described. The spectrometer includes a first conversion screen (8) comprising a neutron absorbing material and a phosphor material, a first wavelength-shifting light-guide (14) arranged to receive photons from the phosphor material of the first conversion screen and generate wavelength-shifted photons therefrom and a first photodetector (22)optically coupled to the first wavelength-shifting light-guide and arranged to detect the wave- length-shifted photons. The spectrometer further includes a second conversion screen (12) comprising a neutron absorbing material and a phosphor material, a second wavelength-shifting light-guide (16) arranged to receive photons from the phosphor material of the second conversion screen and generate wavelength-shifted photons there- from, and a second photodetector (24) optically coupled to the second wavelength-shifting light-guide and arranged to detect the wave- length-shifted photons. A neutron moderator material is arranged between the first and second conversion screens to moderate neutrons.
A radiation detector for neutrons and gamma-rays is described. The detector includes a conversion screen (4a) comprising a mixture of a neutron absorbing material, e.g. containing 6Li, and a phosphorescent material, e.g. ZnS(Ag) and a wavelength-shifting light- guide (8) arranged to receive photons emitted from the phosphorescent material and generate wavelength-shifted photons therefrom. The wavelength-shifting light-guide is doped so as to form a gamma-ray scintillator material operable to generate scintillation photons in response to a gamma-ray detection event therein. A photodetector (10) is optically coupled to the wavelength-shifting light-guide and arranged to detect the wavelength-shifted photons and the scintillation photons. Signals from the photodetector are processed to distinguish neutron detection events from gamma ray detection events.
A calibration source comprises a radioactive material comprising a radioactive isotope having a decay transition associated with emission of a radiation particle and gamma-rays having a known energy and a solid-state detector, arranged to receive radiation particles emitted from the radioactive material. A gating circuit is coupled to the solid-state detector and is operable to generate a gating signal in response to detection of a radiation particle in the solid-state detector. The gating signal may thus be used as an indicator that an energy deposit in a nearby gamma-ray spectrometer is associated with a decay transitions in the radioactive isotope. Since these energy deposits are of a known energy, they can be used as reference points to calibrate the spectrometer response. Thus with calibration sources according to embodiments of the invention, spectral stabilization may be performed in real time and in parallel with obtaining a spectrum of observed signal events.
A gamma-ray spectrometer comprising a scintillation body (34) for receiving gamma -rays and generating photons therefrom and a photodetector for detecting photons from the scintillation body and generating a corresponding output signal is described. The photodetector comprises a photocathode (26), an anode (28), and a reflecting surface (28A). The photocathode is arranged to receive photons from the source and generate photo - electrons therefrom. The anode is arranged to receive photoelectrons generated at the photocathode and is coupled to a detection circuit / amplifier configured to generate an output signal indicative of the photoelectrons received at the anode. The reflecting surface is arranged so as to reflect photons which have passed through the photocathode without interaction back towards the photocathode to provide the photons with another opportunity to interact with the photocathode, thus enhancing the overall effective quantum efficiency of the detector. The reflector may be specular or diffuse.
09 - Scientific and electric apparatus and instruments
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Software for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionizing radiation
09 - Scientific and electric apparatus and instruments
Goods & Services
Software, equipment and apparatus for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionizing radiation
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
Software for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation; equipment and apparatus for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation. Scientific and technological services and research and design related thereto.
09 - Scientific and electric apparatus and instruments
42 - Scientific, technological and industrial services, research and design
Goods & Services
Software for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation; equipment and apparatus for detecting and identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic or ionising radiation. Scientific and technological services and research and design related thereto.
A method of identifying radioactive components in a source comprising (a) obtaining a gamma-ray spectrum from the source; (b) identifying peaks in the gamma-ray spectrum; (c) determining an array of peak energies and peak intensities from the identified peaks; (d) identifying an initial source component based on a comparison of the peak energies with a database of spectral data for radioactive isotopes of interest; (e) estimating a contribution of the initial source component to the peak intensities; (f) modifying the array of peak energies and peak intensities by subtracting the estimated contribution of the initial source component; and (g) identifying a further source component based on a comparison of the modified array of peak energies with the database of spectral data. Thus a method for identifying radioactive components in a source is provided which does not rely on comparing template spectra with an observed spectrum.
G06F 15/00 - Digital computers in generalData processing equipment in general
G06F 15/18 - in which a program is changed according to experience gained by the computer itself during a complete run; Learning machines (adaptive control systems G05B 13/00;artificial intelligence G06N)
A calibration source (20) for a gamma-ray spectrometer (40) is provided. The calibration source comprises a radioactive material (30) comprising a radioactive isotope having a decay transition associated with emission of a radiation particle and a gamma-ray having a known energy, e.g.Na-22, and a solid-state detector (26A, 26B), e.g. a PIN photodiode, arranged to receive radiation particles emitted from thE radioactive material. A gating circuit (32) is coupled to the solid-state detector and is operable to generate a gating signal in response to detection of a radiation particle in the solid-state detector. The gating signal may thus be used as an indicator that an energy deposit in a nearby gamma-ray spectrometer is associated with a decay transition in the radioactive isotope. Since these energy deposits are of a known energy, they can be used as reference points to calibrate the spectrometer response. Thus with calibration sources according to embodiments of the invention, spectral stabilization (i.e. accounting for a changing spectrometer response, as well as base calibration) may be performed in real time and in parallel with obtaining a spectrum of observed signal events (i.e. the spectrum of interest). Furthermore, this is achieved with little contamination of the spectrum events of interest.
An apparatus for determining a direction to a source of radiation, e.g. a gamma-ray or neutron source at a range of 100 m or more, is described. The apparatus is rotatable, e.g. about a vertical axis, and comprises a plurality of radiation shields and radiation detectors. The radiation shields are separated from one another by gaps to form an alternating series of radiation shields and gaps around a closed path within the plane of rotation for the apparatus. The radiation detectors are arranged to detect changes in radiation passing through gaps between the radiation shields as the apparatus is rotated. In providing a rotatable series of radiation shields and gaps with radiation detectors arranged to detect radiation passing through the gaps in this way, a radiation imager is provided that may be seen as being broadly based on coded mask techniques, but which is sensitive to radiation from all azimuths in its plane of rotation.
A portable gamma-ray detector for indicating the intensity of a source of gamma-rays, the nature of the source, and the direction to the source relative to an axis of the detector. The detector comprises a plurality of scintillation bodies arranged around the pointing axis, for example four scintillation bodies in a two-by-two array and separated from each other by aluminum foil. Thus gamma-rays from different directions are shielded from different ones of the scintillation bodies by the other scintillation bodies. The scintillation bodies are coupled to respective photo-detectors and a processing circuit is configured to receive output signals from the photo-detectors and to provide an indication of the direction to a source relative to the pointing axis of the detector based on the relative output signals from the different photo-detectors. The processing circuit is further operable to determine the intensity of the source from the magnitudes of the output signals, and the nature of the source from a spectral analysis of the output signals.
3) generated by gamma-ray interactions. Selected portions of the scintillation body surface are provided with a reflective layer (46, 60, 80) in planar contact with the scintillation body. Other regions are not provided with a reflective layer. Thus specular reflection is promoted in at the surfaces provided with the reflective layer, while total internal reflection may occur in the regions which are not provided with a reflective layer, hi a scintillation body generally in the form of a plank, the photon detector is coupled to one end, and the regions provided with the reflective layer are the edges of the plank. The scintillation body may be shaped so that it reduced in cross section in a direction away from the photon detector. The spectrometer may include photon detectors coupled to both ends of the scintillation body.
A method of identifying radioactive components in a source comprising (a) obtaining a gamma-ray spectrum from the source; (b) identifying peaks in the gamma-ray spectrum; (c) determining an array of peak energies and peak intensities from the identified peaks; (d) identifying an initial source component based on a comparison of the peak energies with a database of spectral data for radioactive isotopes of interest; (e) estimating a contribution of the initial source component to the peak intensities; (f) modifying the array of peak energies and peak intensities by subtracting the estimated contribution of the initial source component; and (g) identifying a further source component based on a comparison of the modified array of peak energies with the database of spectral data. Thus a method for identifying radioactive components in a source is provided which does not rely on comparing template spectra with an observed spectrum.
A portable gamma-ray detector for indicating the intensity of a source of gamma-rays, the nature of the source, and the direction to the source relative to an axis of the detector. The detector comprises a plurality of scintillation bodies arranged around the pointing axis, for example four scintillation bodies in a two-by-two array and separated from each other by aluminium foil. Thus gamma-rays from different directions are shielded from different ones of the scintillation bodies by the other scintillation bodies. The scintillation bodies are coupled to respective photo-detectors and a processing circuit is configured to receive output signals from the photo- detectors and to provide an indication of the direction to a source relative to the pointing axis of the detector based on the relative output signals from the different photo-detectors. The processing circuit is further operable to determine the intensity of the source from the magnitudes of the output signals, and the nature of the source from a spectral analysis of the output signals.
A gamma-ray detector (42, 52, 72, 92) comprising a large-area plastic scintillation body (44, 64, 74, 94) and a photon detector (38, 58, 68, 78) optically coupled to the scintillation body to receive and detect photons (P1, P2, P3) generated by gamma-ray interactions. Selected portions of the scintillation body surface are provided with a reflective layer (46, 60, 80) in planar contact with the scintillation body. Other regions are not provided with a reflective layer. Thus specular reflection is promoted in at the surfaces provided with the reflective layer, while total internal reflection may occur in the regions which are not provided with a reflective layer, hi a scintillation body generally in the form of a plank, the photon detector is coupled to one end, and the regions provided with the reflective layer are the edges of the plank. The scintillation body may be shaped so that it reduced in cross section in a direction away from the photon detector. The spectrometer may include photon detectors coupled to both ends of the scintillation body.
05 - Pharmaceutical, veterinary and sanitary products
09 - Scientific and electric apparatus and instruments
10 - Medical apparatus and instruments
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[IMAGE CONTRAST AGENTS FOR USE IN MEDICAL IMAGING, RADIO THERAPY AND BIOMEDICAL DIAGNOSIS] COMPUTER HARDWARE AND SOFTWARE FOR IDENTIFYING THE NATURE AND COMPOSITION OF MATERIALS THROUGH THE USE OF SPECTROSCOPY AND IMAGING AND NATURALLY OCCURRING OR SPECIALLY GENERATED SOURCES OF MAGNETIC RADIATION, [POSITRON EMISSION TOMOGRAPHY HARDWARE AND SOFTWARE FOR MEDICAL IMAGING USING RADIO PHARMACEUTICALS OR OTHER SOURCES OF ELECTROMAGNETIC RADIATION] [EQUIPMENT, NAMELY, GAMMA CAMERAS AND GAMMA PROBES FOR MEDICAL IMAGING USING RADIO PHARMACEUTICALS OR OTHER SOURCES OF ELECTROMAGNETIC RADIATION]
05 - Pharmaceutical, veterinary and sanitary products
09 - Scientific and electric apparatus and instruments
10 - Medical apparatus and instruments
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Radiolabelled pharmaceuticals, radio tracers and image contrast agents for use in medical imaging, radiotherapy and biomedical diagnosis. Equipment, including hardware and software, for identifying the nature and composition of materials through the use of spectroscopy and imaging and naturally occurring or specially generated sources of electromagnetic radiation. Equipment, incorporating hardware and software, for medical imaging using radio-pharmaceuticals or other sources of electromagnetic radiation.