Abstract: A detector having a thin film of boron nitride (BN) such as cubic BN, and method, system and array utilizing same are provided. Solid-state p-i-n, deep depletion p-n and Schottky diode detector devices based on a thin film of semiconducting cubic BN are provided. Miniaturized solid-state detectors based on cubic boron nitride have a broad range of applications, both civilian and military.

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 neutron detector including an anode and a cathode. The cathode extends proximate the anode and has a face including boron. The face has varied topography. The varied provides increased surface density.

Abstract: A neutron detector comprises a gas-filled dielectric shell, preferably a glass balloon, having opposite electrodes. An electric field is established whereby ionizing particles may be detected via ionization and current flow in the gas, using a pulse height analyzer or other conventional means. The dielectric shell preferably has low gas permeability and a bulk resistivity in the range of 108 to 1017 ?-m, and is preferably in the millimeter to centimeter size range. Multiple balloons may be arranged in parallel or may be individually addressable by the detector electronics.

Abstract: A radiation detector includes a neutron sensing element having a neutron scintillating material at least partially surrounded by an optical waveguide material; and a photosensing element optically coupled to the neutron sensing element. The photons emitted from the neutron sensing element are collected and channeled through the optical waveguide material and into the photosensing element.

Abstract: An apparatus for detecting at least one of neutron and gamma ray reception and outputting a signal indicative of the reception. A detector is responsive to the at least one of neutron and gamma ray reception. The detector has a cathode, an anode separated by a space from the cathode, and a gas within the separating space. Charge is generated within the gas upon the at least one of neutron and gamma ray reception at the cathode and the charge passes to the anode as a detection. A processing arrangement is operatively connected to the anode for outputting the signal indicative of the detection. A light irradiation arrangement for introducing a light irradiation causes charge within the gas that replicates the charge generated upon detection and that causes output of a signal that replicates the signal indicative of the detection.

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 neutron detector array that includes a hollow member circumscribing an axis and bounding a volume. A divider extends parallel to the axis within the hollow member to divide the volume into a plurality of volume portions. A plurality of anodes extend parallel to the axis; at least one anode within each volume portion. A plurality of cathodes wherein the hollow member has an interior surface and the divider has surfaces that are coated with neutron sensitive material. Also, a neutron detector that includes a hollow cathode bounding a volume portion with at least a partial wedge cross-section, and an anode extending thought the volume portion. An electric field exists during operation of the neutron detector within the volume portion, the electric field varying across the cross-section, and the anode being located at an area of maximum field strength within the field. The detector may be used in the array.

Abstract: A neutron detector has a compound of lithium in a single crystal form as a neutron sensor element. The lithium compound, containing improved charge transport properties, is either lithium niobate or lithium tantalate. The sensor element is in direct contact with a monitor that detects an electric current. A signal proportional to the electric current is produced and is calibrated to indicate the neutrons sensed. The neutron detector is particularly useful for detecting neutrons in a radiation environment. Such radiation environment may, e.g. include gamma radiation and noise.

Abstract: A neutron detector, or array of neutron detectors, and method for fabricating same, having active region comprised of inorganic materials such as semiconductors and/or small particles and/or molecules. The detector active region is comprised of a layer or multi-layer heterojunction structure such as p-n junction wherein at least one layer comprises a composite of host semiconductor material in which neutron sensitizing guest material is distributed in all directions throughout the host semiconductor. This composite layer contains neutron capturing atoms such as 10B, 6Li, 157Gd, 235U, 239Pu, 51V , and 103Rh. The semiconductor host and other semiconductor layers transports carriers excited as a result of neutron absorption in the detector active region.

Abstract: A detector for fast neutrons has been developed which includes 1) selected open structure of solid hydrogen-containing material which converts impinging neutrons into recoil protons; 2) a surrounding gas which interacts with the protons to release electrons; 3) an electric field able to drift the electrons through and away from the open-structure material; and 4) an electron detector which monitors the drifted electrons thereby sensing the original impinging neutrons. This type of detector is advantageous for many applications, including efficient fast neutron detection; large area imaging of fast neutrons for fast neutron radiography; or fast neutron beam profiling.

Abstract: Non-streaming high-efficiency perforated semiconductor neutron detectors, method of making same and measuring wands and detector modules utilizing same are disclosed. The detectors have improved mechanical structure, flattened angular detector responses, and reduced leakage current. A plurality of such detectors can be assembled into imaging arrays, and can be used for neutron radiography, remote neutron sensing, cold neutron imaging, SNM monitoring, and various other applications.

Abstract: High-efficiency neutron detector substrate assemblies comprising a first conductive substrate, wherein a first side of the substrate is in direct contact with a first layer of a powder material comprising 10boron, 10boron carbide or combinations thereof, and wherein a conductive material is in proximity to the first layer of powder material; and processes of making said neutron detector substrate assemblies.

Abstract: A multi-stage process utilizing one or more radiation sensors on a distributed network for the detection and identification of radiation, explosives, and special materials within a shipping container. The sensors are configured as nodes on the network. The system supports extended time options at each node and the ability to combine data from multiple nodes for the data acquisition and analysis of shipping containers. The system collects radiation data from one or more nodes and compares the collected data to one or more stored spectral images representing one or more isotopes to identify one or more isotopes present. The identified one or more isotopes present are corresponded to possible materials or goods that they represent. The possible materials or goods are compared with the manifest relating to the container to confirm the identity of materials or goods contained in the container or to detect and/or identify unauthorized materials or goods in the container.

Abstract: A method and system for detecting at least one explosive in a vehicle using a neutron generator and a plurality of NaI detectors. Spectra read from the detectors is calibrated by performing Gaussian peak fitting to define peak regions, locating a Na peak and an annihilation peak doublet, assigning a predetermined energy level to one peak in the doublet, and predicting a hydrogen peak location based on a location of at least one peak of the doublet. The spectra are gain shifted to a common calibration, summed for respective groups of NaI detectors, and nitrogen detection analysis performed on the summed spectra for each group.

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: This generator is equipped with a first alpha particle detector (32) for monitoring the neutrons which are emitted within a first solid angle. According to the invention it is in addition equipped with at least one second alpha particle detector (52) for monitoring the neutrons which are emitted within a second solid angle which is different from the first solid angle. The system allows an object (2) that is placed in the first solid angle to be analysed by means of one or more gamma radiation detectors (34) that are placed in the second solid angle.

Abstract: A radiation detector includes a neutron sensing element comprising a neutron scintillating composite material that emits a first photon having a first wavelength and an optical waveguide material having a wavelength-shifting dopant dispersed therein that absorbs the first photon emitted by the neutron scintillating composite material and emits a second photon having a second, different wavelength, and a functionalized reflective layer at an interface between the neutron scintillating composite material and the optical waveguide material. The functionalized reflective layer allows the first photon emitted by the neutron scintillating composite material to pass through and into the optical waveguide material, but prevents the second photon emitted by the optical waveguide material from passing through and into the neutron scintillating composite material.

Abstract: A neutron detector that includes a hollow member extending along and circumscribing an axis. The hollow member has an interior surface and bounds a volume. The detector also includes an anode extending within the volume. The detector also includes a cathode that includes at least one fin extending within the volume. The fin has a substrate material with at least one surface. At least part of the interior surface of the hollow member and the surface of the at least one fin have neutron sensitive material thereon.

Abstract: A neutron detector including an anode and a cathode. The cathode extends proximate the anode and has a face including boron. The face has varied topography. The varied provides increased surface density.

Abstract: A neutron detector array that includes a hollow member circumscribing an axis and bounding a volume. A divider extends parallel to the axis within the hollow member to divide the volume into a plurality of volume portions. A plurality of anodes extend parallel to the axis; at least one anode within each volume portion. A plurality of cathodes wherein the hollow member has an interior surface and the divider has surfaces that are coated with neutron sensitive material. Also, a neutron detector that includes a hollow cathode bounding a volume portion with at least a partial wedge cross-section, and an anode extending thought the volume portion. An electric field exists during operation of the neutron detector within the volume portion, the electric field varying across the cross-section, and the anode being located at an area of maximum field strength within the field. The detector may be used in the array.

Abstract: A neutron detector includes an anode and a cathode. The cathode circumscribes the anode and has a plurality of planar segments facing the anode. In one embodiment, the neutron detector is part of an array of neutron detectors.

Abstract: A neutron detector that includes an anode and a cathode. The cathode includes at least one portion that has a porous substrate with surface segments that define open pores and a layer of neutron sensitive material on the surface segments of the porous substrate.

Abstract: A method according to one embodiment includes growing an organic crystal from solution, the organic crystal exhibiting a signal response signature for neutrons from a radioactive source. A system according to one embodiment includes an organic crystal having physical characteristics of formation from solution, the organic crystal exhibiting a signal response signature for neutrons from a radioactive source; and a photodetector for detecting the signal response of the organic crystal. A method according to another embodiment includes growing an organic crystal from solution, the organic crystal being large enough to exhibit a detectable signal response signature for neutrons from a radioactive source.

Abstract: One embodiment includes a material exhibiting an optical response signature for neutrons that is different than an optical response signature for gamma rays, said material exhibiting performance comparable to or superior to stilbene in terms of distinguishing neutrons from gamma rays, wherein the material is not stilbene. Another embodiment includes a substantially pure crystal exhibiting an optical response signature for neutrons that is different than an optical response signature for gamma rays, the substantially pure crystal comprising a material selected from a group consisting of: 1-1-4-4-tetraphenyl-1-3-butadiene; 2-fluorobiphenyl-4-carboxylic acid; 4-biphenylcarboxylic acid; 9-10-diphenylanthracene; 9-phenylanthracene; 1-3-5-triphenylbenzene; m-terphenyl; bis-MSB; p-terphenyl; diphenylacetylene; 2-5-diphenyoxazole; 4-benzylbiphenyl; biphenyl; 4-methoxybiphenyl; n-phenylanthranilic acid; and 1-4-diphenyl-1-3-butadiene.

Abstract: Moldable neutron sensitive compositions containing an inorganic scintillating component, and neutron capture component, and a moldable resin component, are described. They are prepared with optimized compositions for maximized thermal neutron sensitivity. Methods for preparing such compositions, and articles and radiation detectors made from them are described as well.

Abstract: A method for calibrating acquired spectra for use in spectral analysis includes performing Gaussian peak fitting to spectra acquired by a plurality of NaI detectors to define peak regions. A Na and annihilation doublet may be located among the peak regions. A predetermined energy level may be applied to one of the peaks in the doublet and a location of a hydrogen peak may be predicted based on the location of at least one of the peaks of the doublet. Control systems for calibrating spectra are also disclosed.

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 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: A directional neutron detecting apparatus includes first and second neutron detectors. Each neutron detector includes a thin planar sheet of neutron-reactive material; a first ohmic electrode operably coupled to one side of the planar sheet of neutron-reactive material; a second ohmic electrode operably coupled to a second side of the planar sheet of neutron-reactive material; a voltage source operably coupled to the first and second ohmic electrodes; and an electrical current detector operably coupled in series between the first ohmic electrode and the voltage source. The first and second neutron detectors are arranged so that their planar neutron-reactive sheets are substantially parallel, opposing and are spaced from each other. Multiple directional neutron detecting apparatuses may be arranged mutually orthogonally to thereby provide omni-directional neutron detection.

Abstract: A neutron detector comprises a gas-filled dielectric shell, preferably a glass balloon, having opposite electrodes. An electric field is established whereby ionizing particles may be detected via ionization and current flow in the gas, using a pulse height analyzer or other conventional means. The dielectric shell preferably has low gas permeability and a bulk resistivity in the range of 108 to 1017 ?-m, and is preferably in the millimeter to centimeter size range. Multiple balloons may be arranged in parallel or may be individually addressable by the detector electronics.

Abstract: A mobile device including a housing, a wireless signal transceiver contained within the housing, and a radiation-detecting structure comprising a charge storage structure contained within the housing to detect radiation.

Abstract: An integrated neutron-gamma radiation detector includes a gamma sensing element, a neutron sensing element comprising a neutron scintillating material at least partially surrounded by an optical waveguide material, and a photosensing element optically coupled to both the gamma sensing element and the neutron sensing element. A portion of the gamma sensing element is capable of being disposed within a central aperture of the neutron sensing element. In one aspect, the neutron sensing element comprises a plurality of cylindrical, concentric shells forming the central aperture for receiving the gamma sensing element. In another aspect, the neutron sensing element comprises a plurality of strands forming a multi-layered structure and forming the central aperture for receiving the gamma sensing element.

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: The present invention relates to a well type neutron counter containing a He-3 detector which includes at least one annular gas layer in a polyethylene moderator, which includes a body formed of a neutron moderator and having a sample cavity for inserting a sample of nuclear material therein; and an annular He-3 detector tube including at least one annular gas layer into which at least He-4 or He-3 gas or their mixture is injected and a plurality of anode rods stood in the annular gas layer with an equal spaces, wherein the He-3 detector tube is formed in an inside of the body so as to surround the sample cavity. The neutron counter has a largely reduced size, simplified structure and resultant decreased failure rate as compared to a conventional counter with a large volume.

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 compact contraband detection system having a radiography device which pre-screens an article subject to inspection to locate regions of interest which may then be further interrogated with a pulsed radiation generator, such as a pulsed fast neutron generator. The pulsed radiation generator includes an integrated particle generator-accelerator having a charged particle generator connected to a compact linear accelerator which produces, injects, and accelerates a charged particle beam. A beam target is provided in the path of the accelerated beam to generate a pulse of interrogating radiation which is directed to the article for interrogation.

Abstract: A microchannel plate for detecting neutrons includes a hydrogen-rich polymer substrate that defines a plurality of channels extending from a top surface of the substrate to a bottom surface of the substrate, where neutrons interact with the plurality of channels to generate at least one secondary electron. A top electrode is positioned on the top surface of the substrate and a bottom electrode is positioned on the bottom surface of the substrate. A resistive layer is formed over an outer surface of the plurality of channels that provides ohmic conduction with a resistivity that is substantially constant. An emissive layer is formed over the resistive layer. Neutron interaction products interact with the plurality of channels defined by the substrate and the emissive films to generate secondary electrons that cascade within the plurality of channels to provide an amplified signal related to the detection of neutrons.

Abstract: A system for interrogating a package, container, vehicle, or similar examination article for the presence of nuclear material. The system typically includes a source of photo-fission energy configured to irradiate the examination article and trigger fission of a fissile or a fissionable material present in the examination article and generate a plurality of fission products, wherein at least one of the plurality of fission products produces a plurality of fission neutrons. A neutron-to-gamma-ray-converter material may be configured to capture up to all of the plurality of fission neutrons and upon capture to emit internal gamma radiation. A gamma radiation detector is typically configured to detect at least a portion of the internal gamma radiation.

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: 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: 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: Method and apparatus is provided for monitoring an item for radioactive material on or associated with the item, the apparatus including an enclosed volume, an item monitoring location, a detection location, ion detectors provided within the detection location, a mover of gas for providing a flow of gas past the item monitoring location to a detection location, so as to revel the level and/or presence of radioactive material on the item. The item may be supported within the monitoring location by one or more rollers to ease its insertion and/or removal. The item monitoring location may be extremely elongate so as to measure pipes and the like. Various designs of roller and gas flow controllers are provided to optimize monitoring.

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: The invention relates to a detector for detecting electrically neutral particles. The detector has a housing (10) filled with a counting gas. A converter (22) in the housing (10) generates conversion products as a result of the absorption of the neutral particles. The conversion products generate electrically charged particles in the counting gas, and a readout device (19) detects the electrically charged particles. A device (18) generates an electrical drift field for the electrically charged particles in a region of the volume of the counting gas so that at least some of the electrically charged particles drift toward the readout device (19). The converter device (22) is of charge-transparent design and being arranged in the detector housing (10) so that the drift field passes through at least part of this device.

Abstract: A well logging instrument includes a source of high energy neutrons arranged to bombard a formation surrounding the instrument. A scintillator sensitive to gamma radiation resulting from interaction of the high energy neutrons with the formation is disposed in the instrument. A neutron shielding material surrounds the scintillator. A neutron moderator surrounds the neutron shielding material. An amplifier is optically coupled to the scintillator.

Abstract: Non-streaming high-efficiency perforated semiconductor neutron detectors, method of making same and measuring wands and detector modules utilizing same are disclosed. The detectors have improved mechanical structure, flattened angular detector responses, and reduced leakage current. A plurality of such detectors can be assembled into imaging arrays, and can be used for neutron radiography, remote neutron sensing, cold neutron imaging, SNM monitoring, and various other applications.

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 cargo inspection system and active inspection methods for operating the same to confirm or clear a presence of explosives and/or nuclear materials in cargo. The active inspection methods use high-energy photons and/or neutrons to induce fission, and measure prompt neutrons, delayed neutrons, and delayed gamma-rays. Additionally, if one or more suspect objects are identified within the cargo with a preceding radiographic or computed tomography scan, a microprocessor calculates a position that produces optimal active inspection signals. The cargo or one of a primary radiation source, a secondary radiation source, or one or more radiation detectors are moved to this calculated position before fission occurs.