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79results about "Measurement by spectrometry" patented technology
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A method and apparatus for detection of radioactive materials
InactiveUS20070001123A1Enhanced gamma ray sensitivityReducing background radiation interferenceMeasurement by spectrometryMaterial analysis by optical meansImage resolutionHigh energy
In the present invention there is a provided an array of radiation detectors comprising at least one detector capable of detecting both low and high energy gamma radiation and adapted to provide spectrometric identification of the gamma source; at least one detector capable of detecting and providing spectrometric identification of fast neutrons and low resolution gamma spectra; at least one detector adapted to detect thermal neutrons; and, at least one plastic scintillator to give enhanced gamma ray sensitivity.
Owner:BUBBLE TECH INDS
Detection of Special Nuclear Material and Other Contraband by Prompt and/or Delayed Signatures from Photofission
InactiveUS20140270034A1Reduce detectionMeasurement by spectrometryNuclear radiation detectionPrompt neutronPhotofission
In accordance with embodiments of the invention, at least the potential presence of Special Nuclear Material (“SNM”) is determined by the detection of prompt neutrons, prompt gamma rays, delayed neutrons, and / or delayed gamma rays from photofission, via time-of-flight (“TOF”) spectroscopic methods. Methods and systems are disclosed.
Owner:VAREX IMAGING CORP
Neutron spectrometer
ActiveUS20140151567A1Wide applicationMeasurement by spectrometryMaterial analysis by optical meansNeutron energy spectrumScintillator
A neutron spectrometer that is more accurate, faster, and more-portable than conventional spectrometers includes an organic scintillator responsive to neutrons and gammas and an inorganic scintillator that captures neutrons. A processor receives signals representative of scintillations in the organic scintillator and in the inorganic scintillator and discriminates neutron signals from gamma signals. The processor also determines pulse areas for neutron moderating signals and performs unfolding based on the determined pulse areas to produce a neutron energy spectrum and / or dose information.
Owner:MERRILL CORP
Noble gas detector for fissile content determination
ActiveUS20130034198A1Raise the possibilityConversion outside reactor/acceleratorsMeasurement by spectrometryNoble gasGas detector
A method and a system for fissile content measurement that utilizes a detector configured to detect fast neutrons. An external radiation source may be used to induce fission in a sample to allow the measurement of a fissile material of the sample with a low spontaneous fission probability. Analyzing the sample may be based on the energy spectrum of emitted neutrons. That is, the energy information regarding the energy of the fast neutrons is obtained, and the fast neutrons as having a high likelihood of originating in a nuclear fission process as opposed to originating in an (alpha,n) reaction by utilizing the obtained energy information are classified to analyze the sample. Alternatively, a position of interaction in the detector of neutron emitted by the sample is measured, and this position is retraced back through intervening material(s) between the detector and the sample to determine the spacial geometry of the sample.
Owner:RAYTHEON CO +1
Fast neutron spectrum measurement system and method
The invention provides a fast neutron spectrum measurement system and method. The system mainly comprises a target material and a gamma spectrum instrument, wherein a to-be-measured neutron and nuclide in the target material react to generate characteristic gamma rays having the Doppler-broadening effect, and to-be-measured neutron spectrum can be acquired through measuring and analyzing the broadening gamma pulse amplitude spectrum. The system is advantaged in that the system is simple and simple, neutron spectrum measurement is converted into gamma spectrum measurement, and high measurement precision is realized.
Owner:PEKING UNIV +1
Spectroscopic fast neutron detection and discriminating using li-based semiconductors
InactiveUS20100327170A1Measurement with semiconductor devicesMeasurement by spectrometrySemiconductor materialsElectric field
A neutron sensing material detector includes an anode; a cathode; and a semiconductor material disposed between the anode and the cathode. An electric field is applied between the anode and cathode. The semiconductor material is composed of a ternary composition of stoichiometry LiM2+GV and exhibits an antifluorite-type ordering, where the stoichiometric fractions are Li=1, M2+=1, and GV=1. Electron-hole pairs are created by absorption of radiation, and the electron-hole pairs are detected by the current they generate between the anode and the cathode. The anode may include an array of pixels to provide improved spatial and energy resolution over the face of the anode. The signal value for each pixel can be mapped to a color or grey scale normalized to all the other pixel signal values for a particular moment in time. A guard ring or guard grid may be provided to reduce leakage current.
Owner:GENERAL ELECTRIC CO
Method and apparatus for neutron detection
ActiveUS20140158893A1Measurement with semiconductor devicesMeasurement by spectrometrySemiconductor detectorSemiconductor
Embodiments of the present invention provide a neutron spectrometry system, comprising a plurality of semiconductor detector portions arranged in close proximity, wherein the detector portions are arranged in at least two non-parallel axes, wherein each detector portion is arranged to output a detection signal indicative of energy deposited in the detector portion by ionising particles induced in the device by incident neutrons, and a control unit arranged to receive the plurality of detection signals, and to allocate detection signals to one or more of a plurality of channels based on a number of substantially coincident detection signals for determining a spectrum of incident neutrons based thereon.
Owner:UK RES & INNOVATION LTD
2-d-tof-pulse neutron detector
InactiveUS20140077093A1Measurement by spectrometryMaterial analysis by optical meansReadout integrated circuitIntegrated circuit
The present invention presents a 2-D-TOF-pulse neutron detector which is able to measure accurate energy spectra, doses, 2-D incident positions and transmission image by measuring TOF of pulse neutron for BNCT and to display the result of the measurement on the transmission image.The 2-D-TOF-pulse neutron detector includes a GEM-detector being put in a chamber filled with electrolytic-dissociative gas, 2-D-TOF readout integrated circuit and image processor.
Owner:HIGH ENERGY ACCELERATOR RESEARCH ORGANIZATION
Inelastic background correction for a pulsed-neutron instrument
ActiveUS20090242746A1Measurement by spectrometryMaterial analysis using neutronsNeutron emissionNeutron
A method for correcting data collected with a neutron emitting instrument, includes: obtaining characterization data for the instrument, the characterization data including inelastic background data of the instrument; and correcting the collected data according to the characterization data. A computer program product and an instrument are provided.
Owner:BAKER HUGHES INC
Nuclear spectrum processing method and device
ActiveCN110941007AImprove performanceHigh performance energy resolutionX-ray spectral distribution measurementMeasurement by spectrometryNuclear radiationNuclear engineering
The invention discloses a nuclear energy spectrum processing method and device. The device comprises a detector, a nuclear pulse processing module and a nuclear energy spectrum processing module. Thedetector is used for detecting nuclear radiation and converting the nuclear radiation into nuclear pulse signals with corresponding amplitudes. The nuclear pulse processing module is used for formingthe nuclear pulse signal into a narrow pulse and carrying out amplitude analysis on the narrow pulse to generate a nuclear energy spectrum. The nuclear energy spectrum processing module is used for reducing the energy resolution of the nuclear energy spectrum and obtaining the nuclear energy spectrum after the energy resolution is reduced. According to the nuclear energy spectrum processing methodand device provided by the embodiment of the invention, high-performance resolution of the nuclear energy spectrum is realized under the condition of preferentially ensuring the pulse passing capacity.
Owner:BEIJING POWER RESOLUTION TECH CO LTD
Spectrometry Diagnostic Electronic Circuit and Associated Counting System
InactiveUS20070279037A1Reduce riskSpectral/fourier analysisResistance/reactance/impedenceDigital dataMeasurement device
The invention relates to a spectrometry diagnostic electronic circuit comprising digital data detection means corresponding to detected pulses and amplitude measurement means to associate a measured amplitude with a detected pulse (24) , wherein pulse rejection means (25) are used to detect digital data and reject every pulse with a width that exceeds a pulse width threshold (tc) and any new pulse during a programmed time interval (T3), if a first pulse has been detected during the programmed time interval.
Owner:COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
Dose rate measuring apparatus
InactiveUS20130284926A1Weaken energyImprove accuracyDosimetersMeasurement by spectrometryDose ratePeak value
A radiation detector outputs an analog pulse for incident radiation, and a signal processing portion is furnished with a wave height measuring function of converting the analog pulse inputted therein to a digital form and then measuring a peak wave height of the analog pulse and a wave height spectrum measuring function of measuring a wave height spectrum on the basis of measured wave height data, computes a dose rate and mean energy on the basis of measured wave height spectral data, and outputs computation results. The signal processing portion computes the dose rate and the mean energy on the basis of the wave height spectral data in a same wave height range on a same time axis. It thus becomes possible to provide accurate information based on which to determine whether a rise in dose rate is contributed by natural radon and thoron or contributed by a reactor facility.
Owner:MITSUBISHI ELECTRIC CORP
Neutron detector attachment device
ActiveUS8624195B2Measurement with semiconductor devicesMeasurement by spectrometryNuclear engineeringOptical spectrometer
Owner:PRINCETON GAMMA TECH INSTR
Spectrum unfolding method for neutron energy spectrum with integral weight
InactiveCN106569251AIn line with physical realityAccurate and physicallyMeasurement by spectrometryNeutron energy spectrumPhysical reality
The invention provides a spectrum unfolding method for a neutron energy spectrum with integral weight. An activation foil weight factor is introduced into an iterative process, and a new truncation condition and a morbid data culling method are used. Neutron energy spectrum unfolding is accurately completed under a condition consistent with the physical reality. The method is based on statistical theory to deduce that the judgment truncation condition has a theoretical basis and is more in line with the physical reality compared with error truncation and truncation of iteration number of times of other methods.
Owner:NORTHWEST INST OF NUCLEAR TECH
Neutron detector attachment device
ActiveUS20130240743A1Measurement with semiconductor devicesMeasurement by spectrometryGamma ray spectrometerLimited availability
An auxiliary neutron detector apparatus designed for attaching and supplementation to an existing gamma-ray spectrometer adds improved neutron detection capabilities. The apparatus uses the existing detector and so does not require additional detector materials, including 3He, which are required by conventional neutron detector attachments. Because of the cost and limited availability of detector materials, this invention is particularly valuable for upgrading systems without existing neutron detector, and for repairing systems with damaged neutron detectors.
Owner:PRINCETON GAMMA TECH INSTR
Neutron fluorescence with syncrhonized gamma detector
ActiveUS20120037812A1Minimize noise signalQuantity minimizationMeasurement by spectrometryMaterial analysis by optical meansFluorescencePulse period
Method and apparatus for minimizing signal noise (20, 22) in thermal, epithermal, and cold neutron fluorescence processes using neutron flux modulation and gamma ray detector pulse gating synchronized to neutron time of flight (NTOF). The apparatus includes a source (12) of thermal, epithermal, and / or cold neutrons, optionally switched between flux or power settings in various embodiments, a gamma ray detector (14) or detection system capable of either being turned ON and OFF, in some embodiments, or else being told to regard or disregard gamma ray signals (20, 22) in other embodiments, a control mechanism (24), and either a target range detector (26) or a prior measurement of target range, in embodiments where the range remains fixed. The gamma ray detector (14) is synchronized to the NTOF by the control mechanism (24) so that it remains switched OFF during the pulse period of the neutron source (12) and for the subsequent NTOF so that any nuisance signals (20, 22) arriving at the detector (14) during these times are not detected or considered.
Owner:BOSS PHYSICAL SCI
Neutron Imager With Spaced Diamond Detector Arrays
ActiveUS20180120460A1Measurement with semiconductor devicesMeasurement by spectrometryPulse heightNeutron imaging
A neutron detector system, with a detector having a pair of spaced diamond detector layers, sandwiched between outer silicon layers. In response to incident neutrons, the detector system measures pulse heights and response times, and from those measurements, calculates the carbon recoil energy and time of flight of scattered neutrons. This data is further used to calculate a “direction cone”, which represents the approximate angle of arrival of the incident neutron. These direction cones can be used to image neutron events.
Owner:SOUTHWEST RES INST
Neutron detector using gd-based scintillator and wide-bandgap semiconductor photovoltaic
ActiveUS20140264057A1Maximize neutron sensingMaximize gamma ray discriminationMeasurement with semiconductor devicesMeasurement with scintillation detectorsPhotodiodeElectron
An enhanced neutron sensing device, that couples a gadolinium based scintillator with at least two wide bandgap photodiodes to achieve a high sensitivity, low power, and portable neutron detector with high gamma discrimination. Once coupled with electrical signal processing and read-out electrons, the device will output the incident neutron flux in the environment and can be used in locations with known sources of neutrons or for identifying clandestine nuclear materials.
Owner:THE UNITED STATES OF AMERICA AS REPRESENTED BY THE SECRETARY OF THE NAVY
Neutron imager with spaced diamond detector arrays
ActiveUS9958560B1Measurement with semiconductor devicesMeasurement by spectrometryPulse heightNeutron imaging
A neutron detector system, with a detector having a pair of spaced diamond detector layers, sandwiched between outer silicon layers. In response to incident neutrons, the detector system measures pulse heights and response times, and from those measurements, calculates the carbon recoil energy and time of flight of scattered neutrons. This data is further used to calculate a “direction cone”, which represents the approximate angle of arrival of the incident neutron. These direction cones can be used to image neutron events.
Owner:SOUTHWEST RES INST
Neutron fluorescence with synchronized gamma detector
ActiveUS8410451B2Minimize noise signalQuantity minimizationMeasurement by spectrometryMaterial analysis by optical meansFluorescencePulse period
Method and apparatus for minimizing signal noise (20, 22) in thermal, epithermal, and cold neutron fluorescence processes using neutron flux modulation and gamma ray detector pulse gating synchronized to neutron time of flight (NTOF). The apparatus includes a source (12) of thermal, epithermal, and / or cold neutrons, optionally switched between flux or power settings in various embodiments, a gamma ray detector (14) or detection system capable of either being turned ON and OFF, in some embodiments, or else being told to regard or disregard gamma ray signals (20, 22) in other embodiments, a control mechanism (24), and either a target range detector (26) or a prior measurement of target range, in embodiments where the range remains fixed. The gamma ray detector (14) is synchronized to the NTOF by the control mechanism (24) so that it remains switched OFF during the pulse period of the neutron source (12) and for the subsequent NTOF so that any nuisance signals (20, 22) arriving at the detector (14) during these times are not detected or considered.
Owner:BOSS PHYSICAL SCI
Neutron spectrometer
ActiveUS9316753B2Measurement with scintillation detectorsMeasurement by spectrometryNeutron energy spectrumScintillator
A neutron spectrometer that is more accurate, faster, and more-portable than conventional spectrometers includes an organic scintillator responsive to neutrons and gammas and an inorganic scintillator that captures neutrons. A processor receives signals representative of scintillations in the organic scintillator and in the inorganic scintillator and discriminates neutron signals from gamma signals. The processor also determines pulse areas for neutron moderating signals and performs unfolding based on the determined pulse areas to produce a neutron energy spectrum and / or dose information.
Owner:MERRILL CORP
Water pumping and injecting multi-layered concentric sphere neutron spectrometer
A water pumping and injecting multi-layered concentric sphere neutron spectrometer includes a neutron detector, a plurality of shells concentrically provided, and a water pumping and injecting device; wherein an innermost shell surrounds a surface of the neutron detector; gaps are formed between adjacent shells for containing liquid; the shells are made of an aluminum material; a valve is arranged on each of the shells except the innermost shell; the water pumping and injecting device is connected to the valve of each of the shells except the innermost shell, so as to input water into the gaps or output the water from the gaps. Compared with conventional neutron spectrometer, weight of the water pumping and injecting multi-layered concentric sphere device and the neutron spectrum detection system of the present invention is greatly reduced, which is conducive to transportation and utilization. Meanwhile, combination of neutron spectrum data measurement and measurement data are increased.
Owner:SICHUAN XINXIANDA CONTROL & MEASUREMENT CO LTD
Neutron ray detecting system, and method of setting neutron ray detecting system
ActiveUS10082587B1Measurement with scintillation detectorsMeasurement by spectrometryGamma rayNeutron
Owner:SUMITOMO HEAVY IND LTD
Wide-energy-spectrum neutron fluence online monitoring system
ActiveCN112904403AImprove strong measurement accuracyNuclear energy generationMeasurement by spectrometryNuclear engineeringNeutron probe
The invention relates to a wide-energy-spectrum neutron fluence on-line monitoring system. The wide-energy-spectrum neutron fluence on-line monitoring system comprises a neutron probe, a signal acquisition device and a data processing device, wherein the neutron probe comprises a cylindrical moderator, a thermal neutron detector, a fast neutron detector and a shielding layer, and can obtain relatively flat neutron fluence response in an energy range of 1 eV to 20 MeV; the signal acquisition and processing part can realize setting of parameters such as high voltage and magnification times of the detector and real-time online display of neutron fluence. The system can remarkably solve the defect that an existing long neutron counter is heavy in size and has the advantages of being light, portable, high in gamma-ray and X-ray resisting capacity and the like, so that the system can be applied to neutron fluence monitoring of strong neutron radiation fields such as accelerators, fission reactors and fusion test devices.
Owner:HEFEI INSTITUTES OF PHYSICAL SCIENCE - CHINESE ACAD OF SCI
Device and method for measuring flux of fast neutrons
ActiveCN106199678AReduce distractionsEasy DeductionMeasurement by spectrometryMeasurement deviceSecondary neutron
The invention discloses a device and method for measuring the flux of fast neutrons, and the method comprises the following steps: enabling the fast neutrons to be converted into secondary neutrons through employing a high-density polyethylene layer and a titanium layer; collecting secondary neutrons comprising characteristic X rays with the titanium energy 4.51keV; analyzing and processing collected signals; analyzing and displaying the flux of outgoing and incoming fast neutrons. A multichannel analyzer is used for receiving the neutrons and the secondary neutrons generated by the high-density polyethylene layer and the titanium layer, and the method measure the flux of fast neutrons through analyzing the number of the full-energy peaks of the characteristic X rays with the titanium energy 4.51keV in the obtained secondary neutrons. The method is high in measurement precision of the flux of neutrons.
Owner:NANJING UNIV OF AERONAUTICS & ASTRONAUTICS
Method for reducing neutron energy errors in neutron nuclear reaction section measurement
ActiveCN111487671AReduce neutron energy errorEasy to implementMeasurement with scintillation detectorsMeasurement by spectrometryNeutron energy spectrumNuclear engineering
The invention discloses a method for reducing neutron energy errors in neutron nuclear reaction section measurement. For the problem that results (such as counting and energy spectrum of reaction products) of neutron nuclear reaction section measurement are contributed by superposition of neutrons with various energies, the method utilizes the neutron energy spectrum obtained through actual measurement to make the measurement result of the neutron nuclear reaction jointly contributed by neutrons with various energies deconvolved to a certain specific neutron energy through an iterative method,so that the neutron energy error is effectively reduced.
Owner:PEKING UNIV
Inelastic background correction for a pulsed-neutron instrument
A method for correcting data collected with a neutron emitting instrument, includes: obtaining characterization data for the instrument, the characterization data including inelastic background data of the instrument; and correcting the collected data according to the characterization data. A computer program product and an instrument are provided.
Owner:BAKER HUGHES INC
Miniaturized fast neutron spectrometer
PendingUS20210239865A1Measurement with semiconductor devicesElectric discharge tubesNeutron energy spectrumNuclear engineering
An isotropic neutron detector includes a spherical secondary particle radiator component and a plurality of stacked semiconductor detectors, A first semiconductor detector is coupled to at least a portion of the spherical secondary particle radiator component, forming a portion of a first concentric shell thereover. A second semiconductor detector coupled to at least a portion of the first semiconductor detector, forming a portion of a second concentric shell thereover.
Owner:KANSAS STATE UNIV RES FOUND
He-3 neutron proportional counter with internal leakage detection and related method
ActiveUS20080265171A1Early detectionMinimize the possibilityElectric discharge tubesNuclear energy generationAlpha particleEngineering
A radiation detector includes a pressure-tight housing having a peripheral, cylindrically-shaped wall and opposite end closures. An electrode wire extends through a center of the housing, spaced from the cylindrically-shaped wall. A pressurized detector gas fills the housing, and circuit connections to the electrode wire and the housing permits application of an electric potential thereto. The electrode wire is composed of a material providing a source of alpha particles for ionizing the gas within the housing, generating an alpha peak on the output spectrum distinct from the peak generated by incident neutrons. A related method is also disclosed.
Owner:BAKER HUGHES INC
Detection of special nuclear material and other contraband by prompt and/or delayed signatures from photofission
InactiveUS9939550B2Reduce detectionMeasurement by spectrometryNuclear radiation detectionPrompt neutronGamma ray
Owner:VAREX IMAGING CORP
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