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 detector probe for detecting ionising radiation includes at least one detector (14) mounted on a support (12), and an electrically operated source of heat (18) arranged on the support in proximity to the detector so that the temperature of the detector may be changed by operation of the heat source. The detector probe may be used in the manufacture of a level gauge or density profiler.

Abstract: A neutron detector for detecting neutrons includes an exterior shell bounding and sealing an interior volume. The exterior shell serves as a cathode. A central structure extends longitudinally within the exterior shell. The central structure serves as an anode and is maintained at a first voltage. The neutron detector includes an insulating portion extending between the central structure and the exterior shell and longitudinally past a shell end of the exterior shell towards a structure end of the central structure. A guard structure extends circumferentially around an outer insulating surface. The guard structure is positioned on the insulating portion between the shell end and the structure end. The guard structure is maintained at a second voltage such that a leakage current on the outer insulating surface is absorbed by the guard structure. A method of detecting neutrons with the neutron detector is also provided.

Abstract: A radiation detector system/method implementing a corrected energy response detector is disclosed. The system incorporates charged (typically tungsten impregnated) injection molded plastic that may be formed into arbitrary detector configurations to affect radiation detection and dose rate functionality at a drastically reduced cost compared to the prior art, while simultaneously permitting the radiation detectors to compensate for radiation intensity and provide accurate radiation dose rate measurements. Various preferred system embodiments include configurations in which the energy response of the detector is nominally isotropic, allowing the detector to be utilized within a wide range of application orientations. The method incorporates utilization of a radiation detector so configured to compensate for radiation counts and generate accurate radiation dosing rate measurements.

Abstract: A radiation detector dosimeter system/method implementing a corrected energy response detector is disclosed. The system incorporates charged (typically tungsten impregnated) injection molded plastic that may be formed into arbitrary detector configurations to affect radiation detection and dose rate functionality at a drastically reduced cost compared to the prior art, while simultaneously permitting the radiation detectors to compensate for radiation intensity and provide accurate radiation dose rate measurements. Various preferred system embodiments include configurations in which the energy response of the detector is nominally isotropic, allowing the detector to be utilized within a wide range of application orientations. The method incorporates utilization of a radiation detector so configured to compensate for radiation counts and generate accurate radiation dosing rate measurements.

Abstract: A method for detecting the presence of a chemical element in an object by emission of neutrons onto the object, characterized in that the emission of neutrons onto the object is constituted, firstly, by a continuous emission of neutrons originating from an associated particle neutron generator (G1) and, secondly, by an emission of neutron pulses which are superimposed on the continuous emission of neutrons, where the neutron pulses originate from a pulsed neutron generator (G2) which generates neutron pulses of pulse duration T2, where two successive neutron pulses are separated by a duration T4, and where the continuous and pulsed emissions of neutrons on to the object produce a gamma capture radiation and an inelastic gamma radiation.

Abstract: A material according to one embodiment exhibits 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, the material comprising a molecule selected from a group consisting of: two or more benzene rings, one or more benzene rings with a carboxylic acid group, one or more benzene rings with at least one double bound adjacent to said benzene ring, and one or more benzene rings for which at least one atom in the benzene ring is not carbon.

Abstract: The mobile radio unit (phone, smartphone) comprises body 16 with an incorporated processor 1. The processor 1 is connected with memory 2, display 3, audible alarm aids 4, keyboard 5, power unit 6, navigator 9, and transceiver 15. The radio unit is equipped with radiation detector 8, electronic amplifier 7 and interface 10 connected to the processor 1. The detector 8 provides measuring alpha-, beta-, gamma- and neutron emissions and solar radiation levels. The processor 1 is provided with software, which ensures both communication functions and control, warning of exposure levels, measuring background radiation, building diagrams illustrating state of human organs. The keyboard 5 comprises keys for dosimeter and/or radiometer mode control. The detector 8, the interface 10 and the amplifier 7 can be placed in the mobile unit body 16 or in separate detachable unit. Thus, there was constructed an efficient mobile unit, which ensures an extended functionality.

Abstract: A neutron detector comprises at least two conductive cathode sheets lying parallel to one another and coated with neutron reactive material on at least one side thereof; dielectric material separating the cathode sheets and covering less than about 80% of their surface area; and a plurality of anode wires lying generally parallel to the cathode sheets and separated from them by the dielectric, with the distance between adjacent anode wires being no more than twenty times the distance between said cathode sheets. The cathode sheets may be flat or curved; they may be separate plates or they may be successive folds or windings of a single folded or spiral-shaped metal sheet. Related methods for building the detector are disclosed.

Abstract: A system is provided. The system includes a conveyor apparatus configured for conveying a material and a water content measurement system positioned about the conveyor apparatus for determining water content in the material. A dimension characteristic measurement system for detecting one or more dimension characteristics of the material is provided and a computer device is configured to manipulate data received from the water content measurement system and the dimension characteristic measurement system to determine a water content of the material.

Abstract: An apparatus and a process are disclosed for straw tube formation utilized in manufacturing boron coated straw neutron detectors. A preferred embodiment of the process for creating a thin walled straw for use in a boron-coated straw neutron detector comprises providing foil having a boron coating on a surface, forming the coated foil into a cylindrical tube having a longitudinal seam and the boron coated surface on the inside of the cylindrical tube, and then ultrasonically welding closed the seam of the tube. Optionally, the cylindrical tube can then be drawn through a die to form a straw tube having a non-circular cross section, preferably a star-shaped cross section.

Abstract: The invention is a method of depositing a solid layer (1) of boron on a metal support (2, 3) intended for a neutron detection apparatus (0) characterized in that it comprises at least one step of depositing at least one layer (1) comprising boron on the metal support (2, 3) and a step of cold-pressing of the metal support (2, 3) with the layer (1) comprising boron.

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: A method of non-destructive inspection of a subject body including one or more elements comprises irradiating the subject body with a neutron ray along an axis line passing through a reference point; synchronously detecting gamma rays from directions inclined at equal angles to the axis line at a plurality of measurement points disposed to have equivalent intervals radially from the axis line, respectively; measuring the detected gamma rays in a plurality of energy ranges; determining whether measured values in the respective energy ranges are beyond thresholds; determining energy ranges where all the measured values are beyond the thresholds; analyzing a type of an element from the determined energy ranges; and detecting a location of the analyzed type of the element in the subject body on the basis of the reference point, the respective measurement points, a relative position relative to a surface of the subject body, and the directions.

Abstract: Disclosed is a pixilated neutron detector including one or more pixel-cells defined by a plurality of perimeter walls, the pixel cells including a cathode and an anode, the cathode being at least one wall of the pixel-cell, the cathode being lined with an interaction material, the anode disposed inside the pixel-cell, the cathode and anode structured to provide an electrical field within the pixel-cell to collect charged particles released by neutrons interacting with the interaction material lining, and a signal processing chain communicably coupled to each of the one or more pixel cells to transmit a signal indicative of a neutron interaction event within the pixel-cell, the signal processing chain including analog signal processing electronics communicably coupled to digital signal processing electronics.

Abstract: A method for detecting a neutron includes providing a first voltage to an input electrode of a microchannel plate, providing a second voltage to an output electrode of the microchannel plate, the second voltage being more positive than the first voltage, measuring a signal on the output electrode, and detecting a neutron based on a comparison of the signal at the output electrode with a baseline value.

Abstract: A system for detecting fissile materials which utilizes boron coated straw detectors in which the straws have non-circular cross sections. Embodiments include straws having star shaped cross sections of various configurations including a six pointed star. The system can include tubular housings having one or more shaped straws stacked within the housings.

Abstract: A boron-coated neutron detector, comprising a cathode tube with a plurality of passages formed therein along its longitudinal direction, the inner wall of each passage being coated with boron material; an electrode wire serving as an anode and arranged longitudinally in each of the passages, the electrode wire adapted to be applied with high voltage; and an insulating end plate to which each end of the cathode tube is fixed, the electrode wire being fixed to the cathode tube via the insulating end plate. Preferably, the cathode tube is formed by jointing a plurality of boron-coated substrates. The boron-coated neutron detector increases the detection efficiency of the neutron detector, which may reach or even exceed the detection efficiency of the 3He neutron detector of the same size, and the cost thereof is much cheaper than the 3He neutron detector.

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 neutron spectrometer is disclosed, which consists of a Helium-3 proportional counter connected by cable to signal and data processing circuits, and a series of moderator shells and moderator lids. The series of cylindrical moderator shells are designed to fit within one another, like Russian Matryoshka dolls, with the counter at the center. Small air gaps are introduced between the shells so that removal of one shell from another is facilitated. The counter is placed within the smallest cylindrical moderator shell, and then a circular lid matching the smallest shell is placed on the opening of the first shell to close the first shell. This first closed shell is then placed within a second shell, which shell is closed with its corresponding circular lid. The cable is routed through the series of shells. A method for using the invention is also disclosed, wherein the counter reading is taken from the fully-assembled neutron spectrometer.

Abstract: A nuclear tool includes a tool housing; a neutron generator disposed in the tool housing; and a solid-state neutron monitor disposed proximate the neutron generator for monitoring the output of the neutron generator. A method for constructing a nuclear tool includes disposing a neutron generator in a tool housing; and disposing a solid-state neutron monitor proximate the neutron generator for monitoring the output of the neutron generator.

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: The present application provides a method for analyzing a raw material for manufacturing of gypsum products, analyzing a plurality of gypsum products, and the gypsum products produced therefrom. Desirably, the analyzing of the raw material is conducted using prompt gamma neutron activation analysis.

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), characterized 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: 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 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 detecting device using a neutron-reactive material as the source of charged particles to feed conventional dynode-based electron multiplier which not gas-filled (i.e., with 3He). The detector comprises a neutron-reacting material that produces charged particles, coupled with an electron multiplier that is known for use in photomultipliers. The neutron-reacting material is deposited on a substrate at the entrance to the electron multiplier. Charged particles from the neutron-reacting material impinge on the first dynode of the electron multiplier, where, in turn, electrons are generated. The secondary electrons are collected by a second dynode, and the charge so collected is amplified in each succeeding dynode stage in a cascade effect. The charge pulse from the anode is processed by subsequent pulse processing electronics and counting electronics to provide a count rate that is proportional to the neutron flux incident on the neutron-reacting material.

Abstract: A method of operating a radiation-detecting device includes charging a first charge storage region of a charge storage structure to place a first charge value at the first charge storage region, and charging a second charge storage region of the charge storage structure to place a second charge value at the second charge storage region. The method further includes conducting a first read operation to determine a change in the first charge value at the first charge storage region at a first time after charging the first charge storage region, and determining a first radiation flux value for an environment containing the charge storage structure based on the change in the first charge value at the first time.

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 arrangement for detecting energy particle impingement includes a support frame and a multi-tube detector pack. Each pack includes multiple detector tubes. Each tube contains at least one sensitive material. Each tube is elongate along a respective axis. The tubes extend parallel with the respective axes being co-planar. Each pack includes mounting tabs located at each axial end. The tabs provide support for the tubes within the pack. At least one of the tabs has at least one securing portion and at least one adjusting portion. Each pack includes at least one operable securing member extending from the respective securing portion to the frame. Operation of the securing member secures the pack to the support frame. Each pack includes at least one operable adjusting member extending from the respective adjusting portion to the frame. Operation of the adjusting member changes an orientation of the pack.

Abstract: A method for providing a boron-lined neutron detector. The method includes providing a boron-containing material and providing water. The method includes mixing the boron-containing material into the water to create a water-based liquid mixture and providing a substrate of a cathode of the neutron detector. The method includes applying the water-based liquid mixture to the substrate of the cathode and removing water from the water-based liquid applied to the substrate to leave a boron-containing layer upon the substrate that is sensitive to neutron impingement. The step of providing a boron-containing material may be to provide the material to include B-10.

Abstract: Methods for manufacturing solid-state thermal neutron detectors with simultaneous high thermal neutron detection efficiency (>50%) and neutron to gamma discrimination (>104) are provided. A structure is provided that includes a p+ region on a first side of an intrinsic region and an n+ region on a second side of the intrinsic region. The thickness of the intrinsic region is minimized to achieve a desired gamma discrimination factor of at least 1.0E+04. Material is removed from one of the p+ region or the n+ region and into the intrinsic layer to produce pillars with open space between each pillar. The open space is filed with a neutron sensitive material. An electrode is placed in contact with the pillars and another electrode is placed in contact with the side that is opposite of the intrinsic layer with respect to the first electrode.

Abstract: An embodiment of the present disclosure provides a method and apparatus for neutron detection. The method comprises receiving neutrons into a number of sensing layers of a plurality of diodes of a number of arrays. Each diode has a sensing layer. A plurality of reactions between the neutrons and each sensing layer of the number of sensing layers are captured in a set of layers for each sensing layer in the number of sensing layers. Each sensing layer is located between the set of layers for each sensing layer. Each set of layers are intrinsic. The method also comprises generating a current pulse for each sensing layer of the number of sensing layers in response to capturing the result of a reaction between the neutrons and each sensing layer of the number of sensing layers.

Abstract: Disclosed herein are representative embodiments of methods, apparatus, and systems for performing combined neutron and gamma ray radiography. For example, one exemplary system comprises: a neutron source; a set of alpha particle detectors configured to detect alpha particles associated with neutrons generated by the neutron source; neutron detectors positioned to detect at least some of the neutrons generated by the neutron source; a gamma ray source; a set of verification gamma ray detectors configured to detect verification gamma rays associated with gamma rays generated by the gamma ray source; a set of gamma ray detectors configured to detect gamma rays generated by the gamma ray source; and an interrogation region located between the neutron source, the gamma ray source, the neutron detectors, and the gamma ray detectors.

Abstract: Systems and methods for generating X-rays and neutrons using a single linear accelerator are disclosed. Such system and methods may interrogate an object at times with X-rays and at other times with neutrons, e.g., after suspicious material is detected based on the X-rays. A system may include a single linear accelerator for generating first and second electron beams; first and second targets; a magnet configured to control irradiation of the first and second targets by the first and second electron beams; and a controller that (a) causes the linear accelerator to generate the first electron beam and causes the magnet to direct the beam to first target to generate X-rays; and (b) causes the linear accelerator to generate the second electron beam and causes the magnet to direct the beam to the second target to generate neutrons.

Abstract: An auxiliary neutron detector apparatus designed for attaching and supplementation to an existing gamma-ray spectrometer adds improved neutron detection capabilities. The apparatus uses the existing detector and so does not require additional detector materials, including 3He, which are required by conventional neutron detector attachments. Because of the cost and limited availability of detector materials, this invention is particularly valuable for upgrading systems without existing neutron detector, and for repairing systems with damaged neutron detectors.

Abstract: A neutron measurement apparatus includes: an analog signal processor; a digitizing processor; an FFT calculation processor; and a signal processor. The analog signal processor amplifies alternating current components of detector output signals output from a neutron detector, and filters to remove high frequency components from the output signals, which the digitizing processor digitizes at a constant sampling period in a time series; the FFT calculation processor converts certain of the signals in a time domain from the digitizing processor into signals in a frequency domain, and filters the signals in the frequency domain; and the signal processor selects and extracts signals having required frequency components through the calculation processing on the FFT calculation processor, to calculate power spectral densities of the extracted signals, and to convert the calculated power spectral densities into a neutron measurement value.

Abstract: Surfaces or surface portions incorporated into gas-filled neutron detectors are coated with and/or composed of at least partially, neutron reactive material. The surfaces may be flat or curved fins or plates, foils, porous or filamentary material, or semi-solid material or aerogel. The incorporation of the extended surfaces coated with or composed of neutron reactive material increases the neutron detection efficiency of the gas-filled detectors over conventional coated designs. These surfaces or surface portions increase the amount of neutron reactive material present in the detector over conventional coated designs and, as a result, increase the neutron detection efficiency. The surfaces can be made of conductive, semiconductive or insulative materials. The surfaces are arranged such that they do not detrimentally detract from the main function of a gas-filled detector with particular attention to gas-filled proportional detectors.

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: According to one embodiment, an apparatus for detecting neutrons includes an array of pillars, wherein each of the pillars comprises a rounded cross sectional shape where the cross section is taken perpendicular to a longitudinal axis of the respective pillar, a cavity region between each of the pillars, and a neutron sensitive material located in each cavity region.

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 arrangement for detecting energy particle impingement includes a support frame and a multi-tube detector pack. Each pack includes multiple detector tubes. Each tube contains at least one sensitive material. Each tube is elongate along a respective axis. The tubes extend parallel with the respective axes being co-planar. Each pack includes mounting tabs located at each axial end. The tabs provide support for the tubes within the pack. At least one of the tabs has at least one securing portion and at least one adjusting portion. Each pack includes at least one operable securing member extending from the respective securing portion to the frame. Operation of the securing member secures the pack to the support frame. Each pack includes at least one operable adjusting member extending from the respective adjusting portion to the frame. Operation of the adjusting member changes an orientation of the pack.

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: 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: 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: The present invention provides a method and an apparatus for calibrating a first self-powered neutron detector for long term use in a nuclear reactor core with a second self-powered neutron detector, where the emitter material of the second self-powered neutron detector has a neutron absorption cross-section that is greater than the neutron absorption cross-section of the first emitter material for the first self-powered neutron detector.

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: A 10B neutron detector and an associated method of detecting neutrons. The detector includes an exterior shell bounding and sealing an interior volume, a neutron-sensitive boron coating located on at least part of the exterior shell at the interior volume. One of the boron coating and the exterior shell serves as a cathode, and a central structure located within the interior volume and serves as an anode. The detector includes gas within the interior volume that conducts an electrical energy pulse between the cathode and the anode in response to a neutron impinging upon the neutron-sensitive boron coating. The gas includes a quantity of 3He gas sensitive to neutron impingement and generating an electrical energy pulse for reception by the anode in response to a neutron impinging upon the 3He gas. The method includes detecting at least one neutron via impingement of the neutron upon the 3He gas.

Abstract: A smart device “plug-in” radiation module(s) and/or methods are described wherein the bulk of non-sensor radiation circuitry is off-loaded to the smart device. By attaching the radiation module to the smart device via a power/communication port (for example, the smart device's headphone/microphone jack) robust attachment can be achieved as well as uniformity of attachment across different smart devices. A very small radiation module form factor is obtainable, not to mention a very significant cost reduction, allowing widespread adoption of radiation detectors as well as radiation geo-mapping. Power for the radiation module can be obtained from the smart device's headphone plug, utilizing the audio out (speaker) signal's power. Similarly, input to the smart device can be facilitated via the audio in (microphone) signal. Further, output of the radiation module can be visualized on the smart device, as well as control functions.

Abstract: A neutron detector comprises at least two conductive cathode sheets lying parallel to one another and coated with neutron reactive material on at least one side thereof; dielectric material separating the cathode sheets and covering less than about 80% of their surface area; and a plurality of anode wires lying generally parallel to the cathode sheets and separated from them by the dielectric, with the distance between adjacent anode wires being no more than twenty times the distance between said cathode sheets. The cathode sheets may be flat or curved; they may be separate plates or they may be successive folds or windings of a single folded or spiral-shaped metal sheet. Related methods for building the detector are disclosed.