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.
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.
A method for compensating for substrate variation in measurement of material quantity of a material positioned on a substrate is described. The method includes receiving a detected X-ray signal for a measurement of the material at a position on a surface of the substrate; and determining a material quantity based on the received X-ray measurement signal and a pre-determined set of compensation parameters for the substrate, the set of compensation parameters varying according to the position on the surface of the substrate.
surrogaterealreal) of the LIB material in the real standards. The method further includes assigning to each surrogate standard a surrogate basis weight based on a transmission of radiation through the surrogate standard and the linearizations
G01G 9/00 - Methods of, or apparatus for, the determination of weight, not provided for in groups
G01B 15/00 - Measuring arrangements characterised by the use of electromagnetic waves or particle radiation, e.g. by the use of microwaves, X-rays, gamma rays or electrons
G01G 17/02 - Apparatus for, or methods of, weighing material of special form or property for weighing material of filamentary or sheet form
G01N 9/24 - Investigating density or specific gravity of materialsAnalysing materials by determining density or specific gravity by observing the transmission of wave or particle radiation through the material
G01N 23/02 - 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
G01N 23/06 - 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
5.
CALIBRATION SAMPLE SET AND METHOD FOR LI-ION BATTERY GAUGING SYSTEMS
A method for preparing surrogate calibration standards for web gauging, is provided. The method includes providing linearizations for one or more radiometric gauges, each linearization associated with a radiometric gauge and relating the basis weight of real standards, comprising a lithium ion battery (LIB) electrode material, to transmission of the radiation through the LIB electrode material. The method also includes providing one or more surrogate standards comprising an inert material having an effective Z (Zsurrogate) substantially the same as an effective Z (Zreal) of the LIB material in the real standards. The method further includes assigning to each surrogate standard a surrogate basis weight based on a transmission of radiation through the surrogate standard and the linearizations
G01N 23/06 - 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
H01M 10/42 - Methods or arrangements for servicing or maintenance of secondary cells or secondary half-cells
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.
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.
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.
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.
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.
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.
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.
H02M 3/158 - Conversion of DC power input into DC power output without intermediate conversion into AC by static converters using discharge tubes with control electrode or semiconductor devices with control electrode using devices of a triode or transistor type requiring continuous application of a control signal using semiconductor devices only with automatic control of output voltage or current, e.g. switching regulators including plural semiconductor devices as final control devices for a single load
H02M 3/335 - Conversion of DC power input into DC power output with intermediate conversion into AC by static converters using discharge tubes with control electrode or semiconductor devices with control electrode to produce the intermediate AC using devices of a triode or a transistor type requiring continuous application of a control signal using semiconductor devices only
13.
RADIATION DETECTOR COMPRISING AN ORGANIC SCINTILLATOR
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
The invention relates to a detector (100) for monitoring scrap metal for radioactive components. Said device comprises a gamma detector (140) for detecting gamma radiation (γ), said detector being arranged in a protective housing (102) which can be mounted so as to project into the receiving compartment (8) of a load receiving means (2) receiving the scrap metal, and containing a scintillator (142) as the gamma-sensitive element, which scintillator has a sensitive volume of less than 20cm3.
