Abstract: A radiation detector is described. The detector includes a silicon photomultiplier, a scintillator, and a layer comprising metal that is spaced from the scintillator. The scintillator is arranged to emit light towards the silicon photomultiplier. The layer comprising metal is configured to receive incident light radiation and to provide additional radiation to the scintillator in response to the received incident radiation. A method of forming such a radiation detector is also described.

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 switching mode power supply includes a microcontroller, an interface circuit connected to the controller, and a boost circuit connected to the controller. A feedback circuit is connected to the controller, and an SiPM is connected to the boost circuit and the feedback circuit.

Abstract: A radiation detector includes a printed circuit board and a detector assembly operably connected to the printed circuit board. The detector assembly includes a silicon photomultiplier and an organic scintillator coating applied to a surface of the silicon photomultiplier. A reflective foil covers the organic scintillator coating. A light sealing cover is secured to the printed circuit board such that the silicon photomultiplier and the organic scintillator are encapsulated within the light sealing cover.

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 radiation dosimeter includes a first radiation detector configured to operate in a counting mode, and a second radiation detector configured to operate in a current mode. A processor is configured to calculate a first detected dose of the first radiation detector, a second detected dose of the second radiation detector, and a total dose value using the first detected dose and the second detected dose. An alarm indicates when the total dose value is above a predetermined level.

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 radiation detector includes a printed circuit board and a detector assembly operably connected to the printed circuit board. The detector assembly includes a silicon photomultiplier and an organic scintillator coating applied to a surface of the silicon photomultiplier. A reflective foil covers the organic scintillator coating. A light sealing cover is secured to the printed circuit board such that the silicon photomultiplier and the organic scintillator are encapsulated within the light sealing cover.

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 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: 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.