Abstract: A neutron detector includes a bulk of a neutron moderating material, a first housing consisting of or comprising a gamma ray attenuating material, a second housing consisting of or comprising a gamma ray attenuating material, a first sensor device comprising a gadolinium cover disposed in the first housing, and a second sensor device disposed in the second housing. The first sensor device and the second sensor device are each sensitive to gamma rays. The first housing and the second housing are arranged adjacent to each other in the bulk.

Abstract: Certain embodiments of the invention may include systems, methods, and apparatus for providing anode and cathode electrical separation in detectors. According to an example embodiment of the invention, a method is presented for providing a neutron detector tube. The method may include applying a conductive layer to at least a portion of an inner surface of a non-conductive cathode tube associated with a neutron detector; applying a neutron sensitive cathode coating to at least a portion of the conductive layer; sealing a first portion of the neutron detector tube with a cathode cap; and sealing a second portion of the neutron detection tube with an anode cap.

Abstract: An activation detector for fast-neutrons has a yttrium target exposed to a neutron source. Fast-neutrons which have energy in excess of 1 MeV (above a threshold energy level) generate gamma rays from a nuclear reaction with the yttrium, the gamma rays having an energy level of 908.96 keV, and the resultant gamma rays are coupled to a scintillator which generates an optical response, the optical response of the scintillator is coupled to a photomultiplier tube which generates an electrical response. The number of counts from the photomultiplier tube provides an accurate indication of the fast-neutron flux, and the detector is exclusively sensitive to fast-neutrons with an energy level over 1 MeV, thereby providing a fast-neutron detector which does not require calibration or the setting of a threshold.

Abstract: A photoneutron-x ray source includes a photoneutron conversion target, which outputs both photoneutrons and x-rays simultaneously. The photoneutron-x ray source includes an x-ray generator for generating an x-ray main beam that is applied to the photoneutron conversion target. The photoneutron conversion target generates photoneutrons upon the application of the x-ray main beam to the photoneutron conversion target. The photoneutron conversion target has a body that defines a passageway extending through the body and that is structured such that a first x-ray beam of the x-ray main beam can pass through the passageway without any reaction with the body, while a second x-ray beam of the x-ray main beam can enter the body and react with the body to emit the photoneutrons.

Abstract: This disclosure relates to systems and methods for material discrimination. The systems and methods include a single source that generates both neutrons and photons, and a single imaging array with a common detector that detects the neutrons and the photons generated from the single source. The systems and methods allow for a determination of the contents, and/or the effective atomic number (“Z”) of the contents, of an object without physical inspection of the interior of the object.

Abstract: A method for detecting neutron radiation in accordance with particular embodiments includes exposing a neutron detector array comprising at least one two-dimensional array of neutron detectors to a first scene of interest. The neutron detector array is based on at least one two-dimensional array of microbolometer detectors. The method also includes receiving a plurality of response values from a corresponding plurality of neutron detectors of the neutron detector array. The method further includes generating a comparison value based on the plurality of response values and a baseline response value. The method additionally, includes determining whether more than a first threshold amount of neutron radiation is being generated by the first scene based on the comparison value.

Abstract: A neutron detector includes a shell bounding an interior volume. A portion of the neutron detector serves as a cathode. The detector includes a central structure located within the interior volume and serving as an anode. The detector includes a boron coating on the interior of the wall wherein at least some of the boron coating is heat diffused into the wall from a boron-containing powder to form the boron coating which is sensitive to neutrons. The detector includes an electrical connector operatively connected to the central structure for transmission of a signal collected by the central structure. An associated method of heat diffusing the boron includes subjecting boron-containing powder to an elevated temperature so that a quantity of the boron-containing powder heat diffuses.

Abstract: Embodiments are directed to a digital data acquisition method that collects data regarding nuclear fission at high rates and performs real-time preprocessing of large volumes of data into directly useable forms for use in a system that performs non-destructive assaying of nuclear material and assemblies for mass and multiplication of special nuclear material (SNM). Pulses from a multi-detector array are fed 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, to reduce the latency associated with current shift-register systems. The word is read at regular intervals, all bits simultaneously, with no manipulation. The word is passed to a number of storage locations for subsequent processing, thereby removing the front-end problem of pulse pileup. The word is used simultaneously in several internal processing schemes that assemble the data in a number of more directly useable forms.

Abstract: A system and method for detection of special nuclear materials within a larger space is disclosed and claimed. Gamma rays emitted from special nuclear materials upon neutron interrogation detected. An associated-particle neutron generator provides interrogation neutrons.

Abstract: A neutron detector with monolithically integrated readout circuitry, including: a bonded semiconductor die; an ion chamber formed in the bonded semiconductor die; a first electrode and a second electrode formed in the ion chamber; a neutron absorbing material filling the ion chamber; and the readout circuitry which is electrically coupled to the first and second electrodes. The bonded semiconductor die includes an etched semiconductor substrate bonded to an active semiconductor substrate. The readout circuitry is formed in a portion of the active semiconductor substrate. The ion chamber has a substantially planar first surface on which the first electrode is formed and a substantially planar second surface, parallel to the first surface, on which the second electrode is formed. Desirably, the distance between the first electrode and the second electrode may be equal to or less than the 50% attenuation length for neutrons in the neutron absorbing material filling the ion chamber.

Abstract: Apparatus and methods for operating a neutron gamma fluorescence based system by modulating the interrogating neutron flux (?Illumination) to allow for optimized signal-to-noise ratio (SNR) or to improve other detection parameter such as integration time. The apparatus includes one or more sensing systems to detect the range from the neutron source to an Area Under Investigation (AUI) or other parameters, one or more sensing systems to detect the return signal or signals caused by the interrogating neutrons, and a controller to receive inputs from the sensing systems, process them, and generate neutron beam modulation commands capable of being used by an agile neutron source to adjust its flux rate (?Illumination) and/or other characteristics.

Abstract: A method for detecting neutron radiation in accordance with particular embodiments includes exposing a neutron detector array comprising at least one two-dimensional array of neutron detectors to a first scene of interest. The neutron detector array is based on at least one two-dimensional array of microbolometer detectors. The method also includes receiving a plurality of response values from a corresponding plurality of neutron detectors of the neutron detector array. The method further includes generating a comparison value based on the plurality of response values and a baseline response value. The method additionally, includes determining whether more than a first threshold amount of neutron radiation is being generated by the first scene based on the comparison value.

Abstract: A neutron detection apparatus can include a neutron sensor and a photosensor optically coupled to the neutron sensor. In an embodiment, the photosensor includes a box-and-line photomultiplier, and in another embodiment, the photosensor includes a box-and-grid photomultiplier. The neutron detection apparatus provide unexpectedly better pulse shape analysis, pulse shape discrimination, or both. In a particular embodiment, the neutron may also be configured to detect gamma rays.

Abstract: A scintillator system is provided to detect the presence of fissile material and radioactive material. One or more neutron detectors include scintillator material, and are optically coupled to one or more wavelength shifting fiber optic light guide media that extend from the scintillator material to guide light from the scintillator material to a photosensor. An electrical output of the photosensor is connected to an input of a pre-amp circuit designed to provide an optimum pulse shape for each of neutron pulses and gamma pulses in the detector signals. Scintillator material as neutron detector elements can be spatially distributed with interposed moderator material. Individual neutron detectors can be spatially distributed with interposed moderator material. Detectors and moderators can be arranged in a V-shape or a corrugated configuration.

Abstract: A flux detection apparatus can include a radioactive sample having a decay rate capable of changing in response to interaction with a first particle or a field, and a detector associated with the radioactive sample. The detector is responsive to a second particle or radiation formed by decay of the radioactive sample. The rate of decay of the radioactive sample can be correlated to flux of the first particle or the field. Detection of the first particle or the field can provide an early warning for an impending solar event.

Abstract: Methods for fabricating three-dimensional PIN structures having conformal electrodes are provided, as well as the structures themselves. The structures include a first layer and an array of pillars with cavity regions between the pillars. A first end of each pillar is in contact with the first layer. A segment is formed on the second end of each pillar. The cavity regions are filled with a fill material, which may be a functional material such as a neutron sensitive material. The fill material covers each segment. A portion of the fill material is etched back to produce an exposed portion of the segment. A first electrode is deposited onto the fill material and each exposed segment, thereby forming a conductive layer that provides a common contact to each the exposed segment. A second electrode is deposited onto the first layer.

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 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 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: Techniques, apparatus and systems for detecting particles such as muons for imaging applications. Subtraction techniques are described to enhance the processing of the muon tomography data.

Abstract: A tube-style neutron detector, a panel-style neutron detector incorporating a plurality of tube-style neutron detectors, and a panel-style neutron detector including a plurality of anode wires are provided. A plurality of channels is provided in a neutron detector such that each channel has an inner surface of a coating layer including a neutron-absorbing material. A wire anode is provided at end of each channel so that electrons generated by a charged daughter particle generated by a neutron are collected to detect a neutron-matter interaction. Moderator units can be incorporated into a neutron detector to provide improved detection efficiencies and/or to determine neutron energy spectrum. Gas-based proportional response from the neutron detectors can be employed for special nuclear material (SNM) detection. This neutron detector can provide similar performance to 3He-based detectors without requiring 3He and without containing toxic, flammable, or high-pressure materials.

Abstract: In one embodiment, a neutron detector includes a three dimensional matrix, having nanocomposite materials and a substantially transparent film material for suspending the nanocomposite materials, a detector coupled to the three dimensional matrix adapted for detecting a change in the nanocomposite materials, and an analyzer coupled to the detector adapted for analyzing the change detected by the detector. In another embodiment, a method for detecting neutrons includes receiving radiation from a source, converting neutrons in the radiation into alpha particles using converter material, converting the alpha particles into photons using quantum dot emitters, detecting the photons, and analyzing the photons to determine neutrons in the radiation.

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 multi-component tunable resistive coating and methods of depositing the coating on the surfaces of a microchannel plate (MCP) detector. The resistive coating composed of a plurality of alternating layers of a metal oxide resistive component layer and a conductive component layer composed of at least one of a metal, a metal nitride and a metal sulfide. The coating may further include an emissive layer configured to produce a secondary electron emission in response to a particle interacting with the MCP and a neutron-absorbing layer configured to respond to a neutron interacting with the MCP.

Abstract: A neutron detector includes a photo sensor with an electrical signal output electrically connected with an electrical signal input node of an electrical signal amplifier circuit. A resistive load is electrically connected between the electrical signal input node and a reference voltage node. The resistive load is a smaller resistance than an open circuit input resistance of the electrical signal amplifier circuit at the electrical signal input node thereby reducing the effective input resistance of the amplifier as seen by the photo sensor's electrical signal output. The neutron detector includes a set of scintillation layers connected to a light guide that channels light to the photo sensor. Moderator material is applied around the set of layers reducing thermal neutron absorption within the detector and increasing detector efficiency.

Abstract: Apparatus, systems, and methods may operate to receive incident energy within a chamber defining a first part of an interaction volume that attenuates the incident energy as a function of path length to provide attenuated energy. Additional activity may include simultaneously transforming the attenuated energy characterized by a substantially exponential intensity function into resultant energy characterized by a substantially polynomial intensity function. The transformation may be accomplished using an interacted energy transformation element that defines a second part of the interaction volume, the transformation element operating to intercept the attenuated energy along a plurality of path lengths. Other activity may include transmitting the resultant energy to a receiver. Additional apparatus, systems, and methods are disclosed.

Abstract: There is provided a high-sensitivity organic semiconductor radiation/light sensor and a radiation/light detector which can detect rays in real time. In the high-sensitivity organic semiconductor radiation/light sensor, a signal amplification wire 2 is embedded in an organic semiconductor 1. Carriers created by passage of radiation or light are avalanche-amplified by a high electric field generated near the signal amplification wire 2 by means of applying a high voltage to the signal amplification wire 2, thus dramatically improving detection efficiency of rays. Hence, even rays exhibiting low energy loss capability can be detected in real time with high sensitivity.

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 having a thickness of from about 50 nm to about 250 nm and 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: 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 detecting radiation using an array of cells containing a metastable material together with sensing apparatus and display apparatus.

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

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 security inspection door comprising a narcotic drug/explosive detecting subsystem, a radioactive substance detecting subsystem and a metal detecting subsystem which are provided in a tank body is disclosed, wherein electromagnetic radiation shields are respectively provided around the three detecting subsystems, so that they are isolated from one another and are not interfered with one another. The three detecting subsystems are combined together to form a novel security inspection door, so the narcotic drugs/the explosives, the radioactive substances and the dangerous metal articles can be detected at the same time. Further, electromagnetic radiation shields are respectively provided around the three detecting subsystems, so that the three detecting subsystems are isolated from one another and are not interfered with one another, and thus, the inspection reliability and the inspection accuracy are improved.

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: Methods and devices relating to a radiation detector comprising of a gas chamber having a cathode plate and a substrate separated by a gap. An array of nano-tips deposited on the substrate that forms an anode structure for electron charge collection. An external power source in communication with the cathode plate and the substrate, wherein the external power source is capable of generating a plurality of regions and each region includes an electric field near each nano-tip of the array of the nano-tips that results in initiating a radiation induced controlled discharge of electrons and ions from at least one gas or at least one gas mixture. Finally, the plurality of regions include multiple generated electric fields near tips of the array of nano-tips such as CNTs, that communicatively create a conductive path between the cathode plate and the substrate, the radiation detector is capable of determining at least one radiation property.

Abstract: A diamond substrate having a contact, wherein the contact comprises a diamond-like-carbon (DLC) layer on at least part of a surface of the diamond substrate; and at least one metal layer on at least part of the surface of the DLC layer. Methods for producing the same and devices comprising such a substrate are also described.

Abstract: A preamplifier circuit for processing a signal provided by a radiation detector includes a transimpedance amplifier coupled to receive a current signal from a detector and generate a voltage signal at its output. A second amplification stage has an input coupled to an output of the transimpedance amplifier for providing an amplified voltage signal. Detector electronics include a preamplifier circuit having a first and second transimpedance amplifier coupled to receive a current signal from a first and second location on a detector, respectively, and generate a first and second voltage signal at respective outputs. A second amplification stage has an input coupled to an output of the transimpedance amplifiers for amplifying the first and said second voltage signals to provide first and second amplified voltage signals.

Abstract: Certain embodiments of the invention may include systems, methods, and apparatus for providing anode and cathode electrical separation in detectors. According to an example embodiment of the invention, a method is presented for providing a neutron detector tube. The method may include applying a conductive layer to at least a portion of an inner surface of a non-conductive cathode tube associated with a neutron detector; applying a neutron sensitive cathode coating to at least a portion of the conductive layer; sealing a first portion of the neutron detector tube with a cathode cap; and sealing a second portion of the neutron detection tube with an anode cap.

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: Fissionable materials are distinguished from other high-effective atomic number materials by producing dual-energy x-ray radiation sufficient to cause fission in fissionable materials and directing the dual-energy x-ray radiation sufficient to cause fission in fissionable materials towards a physical region. X-ray radiation and a product of fission from the physical region are sensed. An absorption of the dual-energy x-ray radiation by the physical region is determined based on the sensed x-ray radiation, and whether the physical region includes fissionable material is determined based on the presence of a product of fission.

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: 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 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 method is provided for simplifying the calibration of neutron multiplicity counters. The method includes multiplicity counter dead time correction algorithms that preclude the need for extended calibration steps with known radiation sources. The algorithms include approximations that allow calculation of the counter's efficiency without knowledge of sample source activity or origin.

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: A radiation detector is disclosed. The detector includes a detector element on which electrodes are formed. First and second electrodes are provided at a first surface of the detector element, and are arranged such that, on application of an electric field between the first and second electrodes, a first detector region is formed adjacent the first surface of the detector element. A third electrode is provided on a second surface of the detector element, and is arranged such that, on application of an electric field between the first and third electrodes, a second detection region is formed between the first and second surfaces of the detector element. The first and second detection regions are differently sized for the detection of different types of radiation. Device for detecting radiation, and handheld devices containing such device, are also disclosed.

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: Dual modality detection devices and methods are provided for detecting nuclear material, the devices include a neutron detector including multiple neutron detection modules; and a gamma detector including multiple gamma detection modules, where the multiple neutron detection modules and the multiple gamma detection modules are integrated together in a single unit to detect simultaneously both gamma rays and neutrons.

Abstract: Room temperature operating solid state hand held neutron detectors integrate one or more relatively thin layers of a high neutron interaction cross-section element or materials with semiconductor detectors. The high neutron interaction cross-section element (e.g., Gd, B or Li) or materials comprising at least one high neutron interaction cross-section element can be in the form of unstructured layers or micro- or nano-structured arrays. Such architecture provides high efficiency neutron detector devices by capturing substantially more carriers produced from high energy ?-particles or ?-photons generated by neutron interaction.

Abstract: A system and method for detection of alpha particles generated by a test material in proximity to a light atomic weight element. The system includes a neutron detector that is configured to detect a rate of generation of neutrons produced by an (alpha, n) reaction between the test material and the light atomic weight element. There is also at least one gamma-ray detector configured to measure a rate of generation of 511 keV gamma rays produced by an annihilation reaction triggered by a positron emission from a daughter product of the light atomic weight element. A comparator is configured to compare the rate of generation of neutrons and the rate of generation of 511 keV gamma rays.