Abstract: A dosimeter includes a housing and a printed circuit board positioned within the housing. A silicon photomultiplier is operably connected to the printed circuit board. A scintillator formed of Ce-activated lithium aluminosilicate glass is positioned on the silicon photomultiplier. An optical coupling is positioned between the scintillator and the silicon photomultiplier, and an optical reflector surrounds the scintillator.

Abstract: A dosimeter includes a housing and a printed circuit board positioned within the housing. A silicon photomultiplier is operably connected to the printed circuit board. A scintillator formed of Ce-activated lithium aluminosilicate glass is positioned on the silicon photomultiplier. An optical coupling is positioned between the scintillator and the silicon photomultiplier, and an optical reflector surrounds the scintillator.

Abstract: A dosimeter includes a housing and a printed circuit board positioned within the housing. A silicon photomultiplier is operably connected to the printed circuit board. A scintillator formed of Ce-activated lithium aluminosilicate glass is positioned on the silicon photomultiplier. An optical coupling is positioned between the scintillator and the silicon photomultiplier, and an optical reflector surrounds the scintillator.

Abstract: A portable electronic dosimeter is described that comprises a plurality of detectors each configured to detect a type of ionizing radiation, wherein each detector is associated with an amplifier configured to produce an output in response to a plurality of detected photons of the ionizing radiation and an event counter configured to produce one or more counts in response to the detected photons of the ionizing radiation over an integration time; and a processor configured to receive the one or more counts from each of the counters and determine if there is coincidence of the one or more counts of all the detectors, wherein if there is coincidence the processor is configured to provide an over range alarm signal.

Abstract: 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.

Abstract: A dosimeter includes a housing and a printed circuit board positioned within the housing. A silicon photomultiplier is operably connected to the printed circuit board. A scintillator formed of Ce-activated lithium aluminosilicate glass is positioned on the silicon photomultiplier. An optical coupling is positioned between the scintillator and the silicon photomultiplier, and an optical reflector surrounds the scintillator.

Abstract: A portable electronic dosimeter is described that comprises a plurality of detectors each configured to detect a type of ionizing radiation, wherein each detector is associated with an amplifier configured to produce an output in response to a plurality of detected photons of the ionizing radiation and an event counter configured to produce one or more counts in response to the detected photons of the ionizing radiation over an integration time; and a processor configured to receive the one or more counts from each of the counters and determine if there is coincidence of the one or more counts of all the detectors, wherein if there is coincidence the processor is configured to provide an over range alarm signal.

Abstract: A gamma radiation detecting device includes a scintillation detector that detects gamma radiation, the detector comprising a scintillation material that includes an element that creates, by neutron activation of the element, an isotope that emits gamma radiation, and a processor configured to monitor the gamma radiation emitted by the isotope, thereby detecting exposure of the gamma radiation detecting device to neutron radiation.

Abstract: 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.

Abstract: A gamma radiation detecting device includes a scintillation detector that detects gamma radiation, the detector comprising a scintillation material that includes an element that creates, by neutron activation of the element, an isotope that emits gamma radiation, and a processor configured to monitor the gamma radiation emitted by the isotope, thereby detecting exposure of the gamma radiation detecting device to neutron radiation.

Abstract: 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.

Abstract: A method of verifying the operational status of a neutron detecting device includes at least partially enclosing a neutron detecting device including a neutron detector in a container having outer walls comprising a thermal neutron absorber material, and determining an attenuated neutron count rate of the neutron detecting device. The method then includes removing the neutron detecting device from the container, exposing the neutron detecting device to neutron radiation originating from cosmic ray background, determining an operational neutron count rate of the neutron detecting device, determining a ratio between the operational neutron count rate and the attenuated neutron count rate, and verifying the operational status of the neutron detecting device if the operational neutron count rate is higher than the attenuated neutron count rate by at least a predetermined amount and the ratio is in a predetermined range.

Abstract: A method of verifying the operational status of a neutron detecting device includes at least partially enclosing a neutron detecting device including a neutron detector in a container having outer walls comprising a thermal neutron absorber material, and determining an attenuated neutron count rate of the neutron detecting device. The method then includes removing the neutron detecting device from the container, exposing the neutron detecting device to neutron radiation originating from cosmic ray background, determining an operational neutron count rate of the neutron detecting device, determining a ratio between the operational neutron count rate and the attenuated neutron count rate, and verifying the operational status of the neutron detecting device if the operational neutron count rate is higher than the attenuated neutron count rate by at least a predetermined amount and the ratio is in a predetermined range.

Abstract: An improved radiation detection device measures a broad range of dose rate levels. According to one arrangement, the radiation detection device calculates a radiation value based on, gamma count information representing counts for different energy levels of radiation in a radiation field as well as a radiation intensity indicator value (e.g., photomultiplier tube anode DC current, measured directly by conventional Analog to Digital Converters or indirectly by power or current consumption information indicating how much energy is required to maintain a photomultiplier tube at a constant voltage) that is at least proportional to an amount of overall radiation energy detected in the radiation sample. Based on a combination of the gamma count information and the radiation intensity indicator value, a controller associated with a corresponding radiation detection device can calculate a radiation dose rate associated with the received radiation sample.

Abstract: A detector device for monitoring metal scrap for radioactive components includes a gamma detector for detecting gamma radiation. The gamma detector is disposed in a protective housing which can be mounted in such a way that it projects into a pick-up area of a load suspension device which picks up the metal scrap. The gamma detector contains a scintillator as a gamma-sensitive element with a sensitive volume of less than 20 cm3.

Abstract: The rare earth metal Lutetium in compound form is used in check sources of various shapes and sizes to calibrate and tune radiation detection devices. Radioactive Lutetium-176, a naturally occurring (non man-made) isotope forming part of the Lutetium compound, produces gamma energies of approximately 90, 200, and 300 kilo-electron Volts which are used in the calibration. Such gamma energies are close to the predominant spectral lines of special nuclear materials such as U-235 and Pu-239, which is to be monitored by radiation detection devices. Lutetium in a radioactive calibration source (which is either integrated into the radiation detection device or positioned close to it during calibration) provides benefits including that no reactor or accelerator is required during production or use, for the creation of man-made radioactivity, no dangerous radiation exposure occurs and (because of the long half-life of Lu-176) the radioactive calibration source essentially never needs to be replaced.

Abstract: The rare earth metal Lutetium in compound form is used in check sources of various shapes and sizes to calibrate and tune radiation detection devices. Radioactive Lutetium-176, a naturally occurring (non man-made) isotope forming part of the Lutetium compound, produces gamma energies of approximately 90, 200, and 300 kilo-electron Volts which are used in the calibration. Such gamma energies are close to the predominant spectral lines of special nuclear materials such as U-235 and Pu-239, which is to be monitored by radiation detection devices. Lutetium in a radioactive calibration source (which is either integrated into the radiation detection device or positioned close to it during calibration) provides benefits including that no reactor or accelerator is required during production or use, for the creation of man-made radioactivity, no dangerous radiation exposure occurs and (because of the long half-life of Lu-176) the radioactive calibration source essentially never needs to be replaced.

Abstract: An improved radiation detection device measures a broad range of dose rate levels. According to one arrangement, the radiation detection device calculates a radiation value based on, gamma count information representing counts for different energy levels of radiation in a radiation field as well as a radiation intensity indicator value (e.g., photomultiplier tube anode DC current, measured directly by conventional Analog to Digital Converters or indirectly by power or current consumption information indicating how much energy is required to maintain a photomultiplier tube at a constant voltage) that is at least proportional to an amount of overall radiation energy detected in the radiation sample. Based on a combination of the gamma count information and the radiation intensity indicator value, a controller associated with a corresponding radiation detection device can calculate a radiation dose rate associated with the received radiation sample.

Abstract: A radiation measuring instrument implements an energy ratio technique that utilizes a ratio between a measured radiation count rate and a detected radiation dose rate to determine if an alarm should be signalled to an operator of the device of this invention. The radiation measuring instrument uses an “inorganic” scintillation or radiation detection material, such as a Thallium doped sodium iodide (NaI(TI)) material, which operates in relatively compact or small sizes to detect radiation. The radiation measuring instrument also uses a ratio of two measured parameters to detect gamma radiation from artificial (hidden) radioactive material where the parameters include (i.) a total number of counted or detected gamma particles and (ii.) a measured, detected, or otherwise derived gamma dose rate.

Abstract: A multi-way radiation monitoring and detection system is capable of detecting a radiation source on or within traffic that can travel within M adjacent traffic ways, where M is an integer equal to or greater than a value of 2. The radiation detection system comprises a set of (M+1) radiation detector assemblies with individual radiation detector assemblies of the set of (M+1) radiation detector assemblies respectively positioned at each of two sides of each of the M adjacent traffic ways. A set of M controllers is included and each controller is associated with a respective traffic way of the M adjacent traffic ways. Each controller is coupled to the respective individual radiation detector assemblies positioned at the two sides of the traffic way to which that controller is associated, such that two controllers associated with two adjacent traffic ways couple to the individual radiation detector assembly positioned between those two adjacent traffic ways.