Abstract: A system for detecting radiation using an array of cells containing a metastable material together with sensing apparatus and display apparatus.

Abstract: A system for determining an amount of radiation includes a dosimeter configured to receive the amount of radiation, the dosimeter comprising a circuit having a resonant frequency, such that the resonant frequency of the circuit changes according to the amount of radiation received by the dosimeter, the dosimeter further configured to absorb RF energy at the resonant frequency of the circuit; a radio frequency (RF) transmitter configured to transmit the RF energy at the resonant frequency to the dosimeter; and a receiver configured to determine the resonant frequency of the dosimeter based on the absorbed RF energy, wherein the amount of radiation is determined based on the resonant frequency.

Abstract: A neutron detection system may include a volume of neutron moderating material, and a plurality of solid state neutron detection devices disposed within the volume of neutron moderating material, wherein some of the neutron detection devices suitable for transduction of primary reaction products resulting from a neutron interaction event, wherein some of the solid state neutron detection devices include two or more solid state neutron detection elements, and wherein the solid state neutron detection elements are configured for omnidirectional detection of impinging neutrons.

Abstract: A neutron detector includes a coincidence detector to detect coincidence events in which each coincidence event indicates proximity in time of a first signal and a second signal. The first signal indicates detection of at least one of a neutron or a gamma ray, and the second signal indicates detection of a gamma ray by a gamma ray detector. A data processor identifies detection of neutron radiation based on characteristics of an energy spectrum of the gamma rays associated with the second signals that correspond to the coincidence signals.

Abstract: A neutron detector system including a neutron sensitive reaction layer may be configured to react with incident neutrons to form energetic particles. An energetic particle capturing layer may be configured to capture energetic particles emitted from the neutron sensitive reaction layer and convert the kinetic energy of the captured energetic particles to heat. A microbolometer sensing element responsive to the heat may be configured to detect the incident neutrons.

Abstract: Methods and systems for producing an image. Measurement data is obtained for a coincidence photon event, and a line projector function is generated based on the obtained measurement data. Additional measurement data is obtained for a single photon event, and a cone-surface projector function is generated based on the additional measurement data. An image is reconstructed using the generated line projector function and the generated cone-surface projector function. In another example method for producing an image, a measurement is obtained, and a projector function is generated using the obtained measurement. The generated projector function is modified based on an a priori image. An image is reconstructed using the modified projector function.

Abstract: A system for efficient neutron detection is described. The system includes a neutron scintillator formed with a number of protruding parallel ribs each side of the scintillator, forming a first set of ribs and a second set of ribs. The ribs have a protrusion height that provides a selected neutron absorption efficiency. The system includes a set of wavelength shifting fibers positioned between each adjacent pair of ribs on both the first side and the second side. Each set of wavelength shifting fibers are in optical proximity to the adjacent pair of the ribs that set of fibers are positioned between.

Abstract: A neutron detection system includes a neutron scintillator having a thickness greater than an optimal thickness and less than twice the optimal thickness. The system includes a first layer of wavelength shifting fiber optic elements positioned on a first side of the neutron scintillator. Adjacent fibers of the first layer pass light to distinct photo-multiplication devices. The system further includes a second layer of wavelength shifting fiber optic elements positioned on a second side of the neutron scintillator. Adjacent fibers of the second layer pass light to distinct photo-multiplication devices. The two layers may share photo-multiplication devices or use different sets of photo-multiplication devices. The system includes a controller that distinguishes a neutron radiation event from a gamma radiation event in response to electronic signals from the distinct photo-multiplication devices.

Abstract: A detection system and methods are described for determining whether a target contains a selected substance or device such as an explosive device, illegal drugs, dangerous chemicals, or the like. According to some embodiments, a detection system is comprising a radiation source and one or more detectors. The detection system in this directs radiation from a distance and towards a target suspected to contain a dangerous device or substance. A response is detected from the target. The response is compared to one or more templates that represent known explosives, drugs, dangerous chemicals, or the like. A score may be generated that corresponds to a similarity between the targeted and known substances. When the score indicates that the target substance is likely to be dangerous or contraband, then an alarm or other indication may be generated in some embodiments.

Abstract: An analyzer having a detector and a neutron source assembly adjacent to the detector is disclosed, wherein the neutron source assembly has a neutron source and a shielding source holder.

Abstract: A neutron detector employs a porous material layer including pores between nanoparticles. The composition of the nanoparticles is selected to cause emission of electrons upon detection of a neutron. The nanoparticles have a maximum dimension that is in the range from 0.1 micron to 1 millimeter, and can be sintered with pores thereamongst. A passing radiation generates electrons at one or more nanoparticles, some of which are scattered into a pore and directed toward a direction opposite to the applied electrical field. These electrons travel through the pore and collide with additional nanoparticles, which generate more electrons. The electrons are amplified in a cascade reaction that occurs along the pores behind the initial detection point. An electron amplification device may be placed behind the porous material layer to further amplify the electrons exiting the porous material layer.

Abstract: Disclosed herein are representative embodiments of methods, apparatus, and systems for performing neutron radiography. For example, in one exemplary method, an object is interrogated with a plurality of neutrons. The plurality of neutrons includes a first portion of neutrons generated from a first neutron source and a second portion of neutrons generated from a second neutron source. Further, at least some of the first portion and the second portion are generated during a same time period. In the exemplary method, one or more neutrons from the first portion and one or more neutrons from the second portion are detected, and an image of the object is generated based at least in part on the detected neutrons from the first portion and the detected neutrons from the second portion.

Abstract: The invention provides a method of performing fast neutron detection or spectroscopy comprising selecting at least one isotope which exhibits fast neutron-induced charged particle reactions, selecting a host medium capable of performing radiation energy spectroscopy, combining the isotope and host medium into an interactive spectroscopic combination, exposing the combination structure to radiation comprising fast neutrons to provide a spectroscopic output, which includes at least one peak in the pulse-height spectrum whose height and amplitude correlate to the energy and intensity respectively of the incident neutrons; and processing the output to detect or to provide measurements of the energy and intensity of incident fast neutron radiation. The invention also provides a fast neutron spectrometer for use with the method.

Abstract: A method for determining the spectral and spatial distribution of a braking photon flow along at least one direction in space (x, y, z), characterised in that the method comprises measuring the neutrons resulting from the impact of the braking photons (ph) on at least one conversion target which is moved in the direction (x, y, z) in space. The invention can be used for X-rays, medical imaging, tomography, etc.

Abstract: A neutron detector includes a microchannel plate having a structure that defines a plurality of microchannels, and layers of materials disposed on walls of the microchannels. The layers include a layer of neutron sensitive material, a layer of semiconducting material, and a layer of electron emissive material. For example, the layer of neutron sensitive material can include boron-10, lithium-6, or gadolinium.

Abstract: Apparatus and methods for effectively detecting and locating explosive substances within remote targets, including improvised explosive devices (IEDs). The detection apparatus includes a neutron beam generator, a gamma ray detector, data collection modules and sensors, and a detection processing module. The neutron beam generator includes a fast neutron source, a neutron moderator to slow some or all of the fast neutrons to thermal energies, a partially enclosing neutron shield, and a rotatable neutron shield surrounding the generated neutrons. The neutron shield has an aperture to form a neutron beam directed at a remote target. If the remote target contains explosive substances, gamma rays radiate isotropically from the remote target when it is bombarded by the neutrons. A portion of these gamma rays are intercepted and detected by the gamma ray detector, which is spaced apart from the neutron source.

Abstract: Neutrons can be detected using first information derived from a first charge induced on an input electrode of a microchannel plate and second information derived from a second charge induced on an output electrode of the microchannel plate. For example, a ratio between the first charge and the second charge is calculated, a sum of the first and second charges is calculated, and whether a neutron has been detected can be determined based on the ratio and the sum.

Abstract: The invention relates to a neutron dosimeter comprising a neutron moderator (12), a first radiation detector (14), which is situated in the neutron moderator (12) and is surrounded by a first metal body (28) containing material that can be activated by neutrons, a second radiation detector (16), which is situated in the neutron moderator (12) close to the first radiation detector (14) and is surrounded by a second metal body (30) that substantially cannot be activated by neutrons. The first metal body (28) and the second metal body (30) are designed in such a way that they substantially have the same degree of absorption of photons. The dosimeter also comprises an evaluation circuit, which is connected to the radiation detectors and is equipped to suppress electrical impulses generated by ionising radiation using a pulse intensity that lies below a predefined pulse intensity threshold.

Abstract: Disclosed is a nuclear radiation-warning detector that measures impedance of silver-silver halide on an interdigitated electrode to detect light or radiation comprised of alpha particles, beta particles, gamma rays, X rays, and/or neutrons. The detector is comprised of an interdigitated electrode covered by a layer of silver halide. After exposure to alpha particles, beta particles, X rays, gamma rays, neutron radiation, or light, the silver halide is reduced to silver in the presence of a reducing solution. The change from the high electrical resistance (impedance) of silver halide to the low resistance of silver provides the radiation warning that detected radiation levels exceed a predetermined radiation dose threshold.

Abstract: A detector array includes a plurality of neutron detectors. Each neutron detector includes an anode and a cathode including at least some B-10 boron. The array includes at least one gamma detector engaged against at least one neutron detector within the array. A detector array includes a plurality of detectors engaged against each other. The plurality of detectors includes at least one neutron detector and at least one gamma detector. In one specific example, the at least one neutron detector contains B-10. An associated method adjusts information concerning a value of neutron detection.

Abstract: An electron multiplier includes a neutron-sensitive composition having silicon oxide, lead oxide, boron-10 enriched boron oxide, and yttrium oxide. The composition is capable of interacting with neutrons to form an electron cascade. The electron multiplier can be in the form of a microchannel plate, a microfiber plate, or a microsphere plate.

Abstract: A system for determining an amount of radiation includes a dosimeter configured to receive the amount of radiation, the dosimeter comprising a circuit having a resonant frequency, such that the resonant frequency of the circuit changes according to the amount of radiation received by the dosimeter, the dosimeter further configured to absorb RF energy at the resonant frequency of the circuit; a radio frequency (RF) transmitter configured to transmit the RF energy at the resonant frequency to the dosimeter; and a receiver configured to determine the resonant frequency of the dosimeter based on the absorbed RF energy, wherein the amount of radiation is determined based on the resonant frequency.

Abstract: A detector array includes a plurality of neutron detectors. Each neutron detector includes an anode and a cathode including at least some B-10 boron. The array includes at least one gamma detector engaged against at least one neutron detector within the array. A detector array includes a plurality of detectors engaged against each other. The plurality of detectors includes at least one neutron detector and at least one gamma detector. In one specific example, the at least one neutron detector contains B-10. An associated method adjusts information concerning a value of neutron detection.

Abstract: A non-invasive multi-step process that includes tomography is applied to determine features of a battery.

Abstract: The present invention includes an apparatus and method for neutron radiation detection. The apparatus comprises combining thin walled, boron-coated straw tubes with a plastic moderator material interspersed around the tubes. The method involves using such an apparatus through application of voltage to a central wire running inside the tubes and collecting electrical pulses generated thereby.

Abstract: An instrument for detecting radiation is provided, which comprises an inner core housing a neutron detector, and an outer core comprising a neutron-moderating material, the instrument further including at least one elongate thermal neutron guide located within the outer core and having an inner end that terminates proximal to the neutron detector. In use, the elongate thermal neutron guide channels thermal neutrons towards the neutron detector. Also provided is a method for using said instrument.

Abstract: A portable and/or mobile detector for highly enriched uranium (HEU) and weapon grade plutonium (WGPu) is disclosed the detects HEU and/or WGPu based on neutron induced fission of a portion of the HEU and/or WGPu and detecting delayed neutron and/or ?-rays emission from delayed neutron emitters formed from the induced fission reactions.

Abstract: A device (26) is used which includes a sealed neutron tube, equipped with alpha particle and gamma radiation detectors; the tube is placed in a given position (P1); steps are performed in which neutrons are sent towards the object (24), and in which data provided by the detectors is acquired and processed in order to obtain a three-dimensional mapping of the object. According to the invention, at least one displacement of the device is performed around the object so as to place it in another position (P2, P3, P4), the steps are repeated, each mapping is geometrically correctly so that that it may be updated relative to the set of all mappings, and these are combined together.

Abstract: Methods and systems are provided for determining a characteristic of an atomic particle affecting a programmable logic device (PLD). The PLD is configured to generate a value at one or more outputs. A source generates a packet of atomic particles. The departure from the source is indicated for the packet of the atomic particles. The PLD is impacted with the packet of the atomic particles. A change is detected in the value of one or more outputs of the PLD. The change in the value of the output or outputs is a result of the impact of the PLD by one of the atomic particles from the packet. A time interval is determined between the departure of the packet of the atomic particles from the source and the change in the value of the output or outputs.

Abstract: A neutron multi-detector array feeds pulses in parallel to individual inputs that are tied to individual bits in a digital word. Data is collected by loading a word at the individual bit level in parallel. The word is read at regular intervals, all bits simultaneously, to minimize latency. The electronics then pass the word to a number of storage locations for subsequent processing, thereby removing the front-end problem of pulse pileup.

Abstract: The invention relates to the fact that a common industrial neutron interrogation screening requirement is that a high throughput rate be accommodated by the screening system. The accumulation of elemental abundance ratio spectral data to minimize statistical uncertainty is a function of the neutron flux passing through the subject. If the subject passes through a neutron beam, with a strictly limited time window for exposure, the flux must be sufficient to accumulate the required statistics. The level of neutron flux necessary may exceed the cost effective limits of the selected neutron source means. Exposure time window dilation is disclosed through a class of system configurations which become practical for reduction to practice by utilization of linear neutron source topology neutron generators. This disclosure is concerned with example embodiments which utilize the length, width, thickness and segmentation of the source emission zone within an appropriate neutron source.

Abstract: An accelerator-based neutron tool is provided. The tool includes a deuterium-tritium gas mixture such that the tool outputs a desired ratio of 2.45 MeV and 14 MeV neutrons.

Abstract: A device includes a neutron-sensitive composition. The composition includes, in weight percent, a non-zero amount of aluminum oxide (e.g., approximately 1% to approximately 3.5% aluminum oxide), greater than 12% (e.g., approximately 12% to approximately 17%) boron oxide, greater than approximately 60% silicon oxide (e.g., approximately 62% to approximately 68% silicon oxide), and a non-zero amount of sodium oxide (e.g., approximately 10% to approximately 14% sodium oxide). The device is capable of interacting with neutrons to form an electron cascade.

Abstract: An upper detector and a lower detector that face at least one side of a fuel assembly, on which neutrons are irradiated in a nuclear reactor, and detect radiation are set at a predetermined interval in an axial direction of the fuel assembly. Distributions of radiation signals are measured by the upper detector and the lower detector while the fuel assembly and the upper detector and the lower detectors are relatively moved along the axial direction of the fuel assembly. Soundness of radiation signals measured by the upper detector and the lower detector is determined in every measurement by comparing radiation signal distributions obtained by measuring the same portion in the axial direction of the fuel assembly in a multiplexed manner with the upper detector and the lower detector. Thereafter, relative burn-up is calculated by utilizing the measured radiation signals to measure a burn-up profile.

Abstract: A method of detecting an activator, the method including impinging a receptor material that is not predominately water and lacks a photoluminescent material with an activator and generating Cherenkov effect light due to the activator impinging the receptor material. The method further including identifying a characteristic of the activator based on the light.

Abstract: A method includes detecting a neutron based on a time proximity of a first signal and a second signal. The first signal indicates detection of at least one of a neutron and a gamma ray. The second signal indicates detection of a gamma ray. The method further includes measuring an amount of detected gamma rays, for example, an amount different from an amount detected and associated with the second signal.

Abstract: A radiation detection blanket for use in surveying a broad or irregular area of interest for radiation emissions. Small radiation detectors are affixed to the fabric and distributed relative to its surface area. The detector materials may be of the OSL, TLD, or ERD variety, or may be a combination of OSL, TLD and ERD. Detector materials having varying thicknesses of high Z coatings may be clustered together in the blanket fabric to yield a gamma radiation spectrum. Use of a converter material on the detector material allows the blanket to detect neutron radiation. The blanket includes specialized transmission means for allowing the detector materials to be read individually, by passing the reader along a surface or along an edge of the blanket. A composite radiation measurement is obtained upon reading the individual detectors, allowing determination of the radiation distribution within the object being surveyed by the blanket.

Abstract: A method for monitoring a container or the contents in a volume (39, 47), including allowing at least one of a beta, gamma, neutron, and proton radiation emerging from said container or volume (39, 47), and/or secondary particles or radiation brought forth by said radiation, to pass through a measuring volume (12, 12?) of at least one radiation detector (10, 10?, 10?), said measuring volume (12, 12?) containing a noble gas and/or a noble gas isotope, or a mixture of noble gases and/or noble gas isotopes and detecting the photons generated within said measuring volume (12, 12?) by an interaction (18, W1, . . . , W4) of the radiation with the noble gas or noble gases and/or their isotopes of the measuring volume (12, 12?). The output of said photon detecting means (15, 16, 53) is then used to derive information about the container or the contents in said volume (39, 47), whereby this information is used to discriminate protons, neutrons, beta and gamma rays respectively.

Abstract: A non-invasive multi-step process that includes tomography is applied to determine features of a battery.

Abstract: A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Abstract: An accelerator-based neutron tool is provided. The tool includes a deuterium-tritium gas mixture such that the tool outputs a desired ratio of 2.45 MeV and 14 MeV neutrons.

Abstract: In some embodiments, an electron multiplier includes a neutron-sensitive composition having, in weight percent, approximately 30% to approximately 60% silicon oxide, approximately 20% to approximately 60% lead oxide, and approximately 1% to approximately 15% boron-10 enriched boron oxide. The composition is capable of interacting with neutrons to form an electron cascade. The electron multiplier can be in the form of a microchannel plate, a microfiber plate, or a microsphere plate.

Abstract: A system for detecting and classifying small amounts of explosives and other controlled substances while rejecting confounders, including a source/detector array formed of a plurality of sources and a plurality of detectors, a signal processor coupled to the source/detector array for processing data received from the detectors, a classifier coupled to the signal processor for classifying data received from the signal processor according to a plurality of algorithms, a maximal rejection classifier coupled to the classifier; and a declarative decision module coupled to the maximal rejection classifier for rendering an accurate decision regarding the contents of the object is provided. The apparatus includes an enclosure, a shield layer disposed within the enclosure, a cavity disposed within the shield layer, a plurality of neutron sources and a detection array disposed within the cavity, and a transport mechanism for moving objects through the cavity past the sources and detection array.

Abstract: A neutron detector has a volume of neutron moderating material and a plurality of individual neutron sensing elements dispersed at selected locations throughout the moderator, and particularly arranged so that some of the detecting elements are closer to the surface of the moderator assembly and others are more deeply embedded. The arrangement captures some thermalized neutrons that might otherwise be scattered away from a single, centrally located detector element. Different geometrical arrangements may be used while preserving its fundamental characteristics. Different types of neutron sensing elements may be used, which may operate on any of a number of physical principles to perform the function of sensing a neutron, either by a capture or a scattering reaction, and converting that reaction to a detectable signal. High detection efficiency, an ability to acquire spectral information, and directional sensitivity may be obtained.

Abstract: A two-dimensional detection system for neutron radiation is disclosed. The detection system includes a means (1) for emitting a neutron beam (10), a support means (2) adapted for receiving a sample (3), a photoemission means (5) adapted for being activated by a neutron radiation, and a cooled low light level charge-coupled detection device (7). The emission means (1) emits a monochromatic neutron beam (10). The system further includes a filter means (4), the filter means (4) being located between the support means (2) and the photoemission means (5) and being adapted for trapping at least a substantial part of the monochromatic neutron beam transmitted (12) by the sample (3), and an amplification means (6) located upstream the charge-coupled detection device (7) and coupled with the charge-coupled detection device (7).

Abstract: A method includes detecting a neutron based on a time proximity of a first signal and a second signal. The first signal indicates detection of at least one of a neutron and a gamma ray. The second signal indicates detection of a gamma ray.

Abstract: A process for measuring the moisture content in a quantity of PuO2 powder. The process detects the content of thermal neutrons emitted by the quantity of PuO2 powder and then deduces its moisture content from a value of the detected content assuming a relation determined between the proportion of thermal neutrons emitted by a quantity of PuO2 powder and the known moisture content in this quantity of PuO2 powder.

Abstract: A neutron flux mapping system for a nuclear reactor including: drivers each including a geared motor, a helical gear driven by the geared motor, and a storage reel adapted to supply, to the helical gear, a detector cable carrying a detector; and a double indexing path selector unit including upper and lower fixed plates, a fixed shaft, an outer path selector rotatably mounted to the upper fixed plate, and inner path selectors. The outer path selector includes an upper rotating plate rotatably mounted to the upper fixed plate while carrying a drive unit for rotating the outer path selector about the fixed shaft, and a control unit for controlling the drive unit, and a lower rotating plate connected to the upper rotating plate.

Abstract: A portable survey instrument and methodology yield intensity of neutron radiation, intensity of gamma radiation, and a direction of impinging gamma radiation. The instrument uses a neutron detector surrounded by an essentially rectangular moderator with preferably four gamma ray detectors disposed symmetrically about the neutron detector and within the moderator. Material and dimensions of the moderator are selected so that the neutron measurement is equally sensitive to fast and thermal neutrons. The moderator also induces angular responses to the gamma ray detectors. Responses of the gamma ray detectors are combined to yield a parameter indicative of the angular position of a source. The survey instrument is portable and suited for hand held use.

Abstract: A pulse discrimination method for discriminating between pulses having a short decay period and a long decay period, may comprise: Detecting the pulse; integrating a rise portion of the pulse; integrating a decay portion of the pulse; and comparing the integrated rise portion of the pulse with the integrated decay portion of the pulse to distinguish between a pulse having a long decay period and a pulse having a short decay period.