Abstract: A method for forming a multi-layered, stacked grid structure includes aligning a first grid structure with a second grid structure, wherein both the first grid structure and the second grid structure each include a substrate in which a plurality of trenches are formed and a cured carrier fluid disposed within the plurality of trenches, and wherein a plurality of nano-particles are suspended within the cured carrier fluid. The method also includes, upon aligning the first grid structure and the second grid structure so that their respective plurality of trenches are aligned in the same orientation, joining the first grid structure and the second grid structure together to form the multi-layered, stacked grid structure.

Abstract: A fissile neutron detection system includes an ionizing thermal neutron detector arrangement including an inner peripheral shape that at least substantially surrounds a moderator region for detecting thermal neutrons that exit the moderator region but is at least generally transparent to the incident fissile neutrons. A moderator is disposed within the moderator region having lateral extents such that any given dimension that bisects the lateral extents includes a length that is greater than any thickness of the moderator arrangement transverse to the lateral extents. The moderator can include major widthwise and major lengthwise lateral extents such that any given dimension across the lengthwise and widthwise lateral extents includes a length that is greater than any thickness of the moderator arrangement transverse to the lateral extents.

Abstract: Embodiments of the present disclosure include a system for detecting neutrons with a housing, a gas chamber at least partially defined by the housing, an anode extending through at least a portion of the gas chamber, and a pseudogas arranged within the gas chamber. The pseudogas comprises a mixture of gas and suspended solid particles that contain an element with a high cross-section for thermal neutron capture.

Abstract: A device may include a collimator positioned between a radiation source of a scanner and a bore of the scanner. The bore may include a detecting region configured to accommodate a subject. The collimator may be configured to prevent at least one portion of radiation rays emitted from the radiation source from being incident on the subject. The device may further include a first filter and a second filter. The first filter may be positioned between the radiation source and the collimator. The second filter may be positioned between the collimator and the bore. The first filter and the second filter may be configured to adjust a distribution of radiation impinging upon the subject.

Abstract: The presence of chlorine and nitrogen are determined and measured using a non-invasive portable neutron-generating and gamma ray detecting system(s). Portable devices of the present invention can also be used to detect chlorine and/or nitrogen-containing underground objects rapidly and on-site. Devices and systems described herein can be operated remotely and pre-programmed with search patterns, guided by an operator remotely, or programmed to home in on high-chlorine and/or nitrogen concentration areas.

Abstract: Apparatus for amplifying low level signals within a nuclear plant's containment building, derived from the ex-core nuclear instrumentation system. The system employs vacuum micro-electronic devices in place of conventional pre-amplifier assemblies to position the pre-amplifier assemblies closer to and within the vicinity of the ex-core detector outputs.

Abstract: A narrow thermal neutron detector includes a slidably receivable ionization thermal neutron detector module within an overall housing body. An active sheet layer of the ionization thermal neutron detector module can be tensioned across its width. The ionization thermal neutron detector module can include module upper major surface extents and module lower surface extents such that, when installed within the housing body, the module upper major surface extents are in a first spaced apart confronting relationship with housing upper major surface extents to define a first clearance and module lower major surface extents are in a second spaced apart confronting relationship with housing lower major surface extents to define a second clearance to accommodate housing flexing due to ambient pressure change. The housing body can be formed with a single opening for receiving the ionization thermal neutron detection module or with opposing first and second opposing end openings.

Abstract: A temperature sensor includes: a sheath tube; a pair of thermocouple wires inserted into the sheath tube; a temperature measuring junction of the pair of thermocouple wires; an insulating support disposed in the sheath tube; and a tip protective tube covering the outer periphery of a tip end of the sheath tube to surround the temperature measuring junction. The tip protective tube includes a base-end side tube portion and a tip-end side tube portion, the tip-end side tube portion having a diameter smaller than that of the base-end side tube portion. The tip-end side tube portion has a tip-end side portion filled with a first insulating filler in which the temperature measuring junction is buried. In the remaining part on the inside of the tip-end side tube portion, an air layer is formed.

Abstract: Methods for forming a transition metal nitride film on a substrate by atomic layer deposition and related semiconductor device structures are provided. In some embodiments, methods may include contacting a substrate with a first vapor phase reactant comprising a transition metal precursor and contacting the substrate with a second vapor phase reactant comprising an alkyl-hydrazine precursor. In some embodiments, related semiconductor device structures may include a PMOS transistor gate structure, the PMOS transistor gate structure including a transition metal nitride film and a gate dielectric between the transition nitride film and a semiconductor body. The transition metal nitride film includes a predominant (200) crystallographic orientation.

Abstract: Detectors, a system and a method for detecting ionizing radiation are provided. In some aspects, a detector includes a first layer comprising a first conducting material, and a second layer comprising a second conducting material, wherein at least one of the first layer and second layer is configured to produce secondary particles upon irradiation by an ionizing radiation. The detector also includes a separating layer positioned between the first and second layer configured to transport therebetween at least one of charges associated with the secondary particles and charges produced by the secondary particles, wherein an electric current generated by the charges, and collected between the first and second layer, is indicative of properties the ionizing radiation.

Abstract: A beam shaping assembly for neutron capture therapy includes a beam inlet, a target having nuclear reaction with an incident proton beam from the beam inlet to produce neutrons forming a neutron beam defining a main axis, a moderator adjoining to the target, a reflector surrounding the moderator, a thermal neutron absorber adjoining to the moderator, a radiation shield arranged inside the beam shaping assembly and a beam outlet. The neutrons are moderated to epithermal neutron energies. An outer surface of the moderator includes at least a first tapered section. The reflector leads the neutrons deviated from the main axis back. The thermal neutron absorber is used for absorbing thermal neutrons so as to avoid overdosing in superficial normal tissue during therapy. The radiation shield is used for shielding leaking neutrons and photons so as to reduce dose of the normal tissue not exposed to irradiation.

Abstract: A beam shaping assembly for neutron capture therapy includes a beam inlet, a target having nuclear reaction with an incident proton beam from the beam inlet to produce neutrons forming a neutron beam defining a main axis, a moderator adjoining to the target, a reflector surrounding the moderator, a thermal neutron absorber adjoining to the moderator, a radiation shield arranged inside the beam shaping assembly and a beam outlet. The neutrons are moderated to epithermal neutron energies. The reflector leads the neutrons deviated from the main axis back, and a gap channel is arranged between the moderator and the reflector. The thermal neutron absorber is used for absorbing thermal neutrons so as to avoid overdosing in superficial normal tissue during therapy. The radiation shield is used for shielding leaking neutrons and photons so as to reduce dose of the normal tissue not exposed to irradiation.

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 radiation monitor includes a high-energy count-rate-measurement functional unit, a low-energy count-rate-measurement functional unit, and an alert-diagnosis functional unit. The alert-diagnosis functional unit receives an alert from the high-energy count-rate-measurement functional unit, receives a low-energy count rate from the low-energy count-rate-measurement functional unit, determines whether or not the low-energy count rate is in a set acceptable range by performing synchronizing with alert transmission, determines that the alert is caused by fluctuation, when the low-energy count rate is in the acceptable range, determines that the alert is caused by any of an increase in the ? ray which is a measurement target or enter of noise, when the low-energy count rate is increased beyond the acceptable range, and outputs results of determination.

Abstract: Methods and systems for characterizing particles in an aerosol are disclosed. A system includes a collection container that utilizes the principles of elutriation to collect particles of selected aerodynamic diameter ranges within a measurement region. A particle detector is used to detect and characterize particles that have settled into the measurement region.

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: An atomic particle detection assembly includes one or more detectors that detect atomic particles. The detectors are positioned within a first chamber having a first operating pressure. The atomic particle detection assembly includes a junction apparatus supporting the detectors. The junction apparatus defines a second chamber having a second operating pressure that is different from the first operating pressure. Sensing electronics are attached to the detectors and the sensing electronics are housed within the second chamber of the junction apparatus.

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 neutron spectrometer is described. The spectrometer includes a first conversion screen (8) comprising a neutron absorbing material and a phosphor material, a first wavelength-shifting light-guide (14) arranged to receive photons from the phosphor material of the first conversion screen and generate wavelength-shifted photons therefrom and a first photodetector (22) optically coupled to the first wavelength-shifting light-guide and arranged to detect the wave-length-shifted photons. The spectrometer further includes a second conversion screen (12) comprising a neutron absorbing material and a phosphor material, a second wavelength-shifting light-guide (16) arranged to receive photons from the phosphor material of the second conversion screen and generate wavelength-shifted photons there-from, and a second photodetector (24) optically coupled to the second wavelength-shifting light-guide and arranged to detect the wave-length-shifted photons.

Abstract: The present invention includes a method for radiation detection. The present invention utilized boron-coated detectors as a new alternative to large 3He tubes that will address the timing limitations of 3He-based detectors in active interrogation systems, by providing a 100-times faster ion collection time. This may enable the counting of prompt neutrons starting within 10 ?s following each gamma ray pulse. Current 3He-based detectors can only count delayed neutrons, and the linac pulse rate is severely limited by the lengthy times required to count these very late neutrons. If detection of the prompt component can be achieved, up to 150 times more neutrons can be detected in each pulse and pulse rate can be increased by more than 10 fold, giving a net sensitivity gain of 1500 while using the same detection array and linac.

Abstract: A method of determining directionality of radiation is disclosed which comprises dividing the tensioned metastable fluid liquid volume adjacent to a radioactive source into a plurality of sectors, determining the opposing sector ratio of the respective sector and determining the direction of the radiation based on the opposing sector ratios of the plurality of sectors. The method further comprising determining directionality of incoming radiation from the tension pressure assisted elongation of bubble shapes pointing towards direction of radiation particles that interacted with nuclei of tensioned metastable fluid detector system. A device capable of carrying out these methods is also disclosed.

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: An electrical system for an atomic particle detection assembly includes an electrical component electrically connected to an atomic particle detection unit. The electrical system includes a dielectric insulating material surrounding the electrical component. The electrical system also includes a conductive shielding material surrounding the dielectric insulating material. The conductive shielding material and a conductive element are at substantially the same electric potential.

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 at least one of hafnium (Hf), samarium (Sm), erbium (Er), neodymium (Nd), tantalum (Ta), lutetium (Lu), europium (Eu), dysposium (Dy), or thulium (Tm).

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 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 detector includes an outer shell having a shell profile in which a welded portion of the shell profile extends as an annular flange in an outward direction relative to a center axis of the outer shell. The detector further includes an end cap positioned adjacent the welded portion of the outer shell. The end cap and the welded portion of the outer shell are welded together to form a seal. A method of making a detector is also provided.

Abstract: A method for assessing an alpha particle emission potential of a metallic material. A metallic material is initially subjected to a secular equilibrium disruption process, such as melting and/or refining, to disrupt the secular equilibrium of the radioactive decay of one or more target parent isotopes in the material. A sample of the material is treated to diffuse target decay isotopes within the sample such that the measured alpha particle emission directly corresponds to the concentration or number of target decay isotope atoms within the entirety of the sample, enabling the concentration of target decay isotopes in the sample to be determined. The concentration of target parent isotopes in the material may then be determined from the concentration of target decay isotopes and time elapsed from the secular equilibrium disruption process, and may be used to determine a maximum alpha particle emission that the metallic material will exhibit.

Abstract: A method for a constructing radiation detector includes fabricating a multi-layer structure upon a wafer, the multi-layer structure comprising a plurality of metal layers, a plurality of sacrificial layers, and a plurality of insulating layers, forming a cavity within the multi-layer structure, filling the cavity with a gas that ionizes in response to nuclear radiation, and sealing the gas within the cavity.

Abstract: Methods for building a neutron detector are disclosed, in which the 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.

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 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: An atomic particle detection assembly includes one or more detectors that detect atomic particles. The detectors are positioned within a first chamber having a first operating pressure. The atomic particle detection assembly includes a junction apparatus supporting the detectors. The junction apparatus defines a second chamber having a second operating pressure that is different from the first operating pressure. Sensing electronics are attached to the detectors and the sensing electronics are housed within the second chamber of the junction apparatus.

Abstract: A spherical device for detecting neutrons includes a sphere-shaped cathode and a ball-shaped anode. The cathode forms an enclosure filled with an ionising gas. The ionising gas is pure nitrogen. The ionising gas can also be mixed with a quencher. In this case, the quencher may be ethane.

Abstract: A method and article of manufacture of intermixed tunable resistance composite materials. A conducting material and an insulating material are deposited by such methods as ALD or CVD to construct composites with intermixed materials which do not have structure or properties like their bulk counterparts.

Abstract: An atomic particle detection assembly includes at least one detector that detects atomic particles. The atomic particle detection assembly includes a junction apparatus supporting the detector. The junction apparatus includes a first manifold attached to a first housing at an attachment location. The junction apparatus includes a sealing device sealing the first manifold with respect to the first housing along a sealing axis. The sealing axis is substantially parallel to and separated a first distance (d1) from an attachment axis defined by the attachment location.

Abstract: A detector includes an outer shell having a shell profile in which a welded portion of the shell profile extends as an annular flange in an outward direction relative to a center axis of the outer shell. The detector further includes an end cap positioned adjacent the welded portion of the outer shell. The end cap and the welded portion of the outer shell are welded together to form a seal. A method of making a detector is also provided.

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. 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: 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: Radiation sensitive devices include a substrate comprising a radiation sensitive material and a plurality of resonance elements coupled to the substrate. Each resonance element is configured to resonate responsive to non-ionizing incident radiation. Systems for detecting radiation from a special nuclear material include a radiation sensitive device and a sensor located remotely from the radiation sensitive device and configured to measure an output signal from the radiation sensitive device. In such systems, the radiation sensitive device includes a radiation sensitive material and a plurality of resonance elements positioned on the radiation sensitive material. Methods for detecting a presence of a special nuclear material include positioning a radiation sensitive device in a location where special nuclear materials are to be detected and remotely interrogating the radiation sensitive device with a sensor.

Abstract: A method and apparatus for detecting an isotope. Embodiments can detect radioactive isotopes. Embodiments can utilize a detector that incorporates at least two sub-detectors. Each sub-detector can receive energy from an isotope and create a signal corresponding to the received energy. Each sub-detector can incorporate a detector element, such as a detector element incorporating one or more diodes, a detector element incorporating a crystal, a detector element incorporating a solid-state device, or a detector element incorporating a scintillator. The sub-detectors can be configured such that for each isotope to be detected at least two of the sub-detectors produce different output signals, or readings. In an embodiment, each sub-detector is configured such that when there are at least two sub-detectors exposed to the isotope each of the corresponding readings from the sub-detectors is different from each of the other readings.

Abstract: Solid state neutron detection utilizing gadolinium as a neutron absorber is described. The new class of narrow-gap neutron-absorbing semiconducting materials, including Gd-doped HfO2, Gd-doped EuO, Gd-doped GaN, Gd2O3 and GdN are included in three types of device structures: (1) a p-n heterostructure diode with a ˜30 ?m Gd-loaded semiconductor grown on a conventional semiconductor (Si or B-doped Si); (2) a p-n junction or a p-i-n trilayer diode with a Gd-loaded semiconductoron one side and single-crystal semiconducting Li2B4O7 layer on the other side of the heterojunction; and (3) a p-n junction or a p-i-n trilayer diode with a Gd-loaded semiconductoron on one side and a boron nitride (BN) semiconductor layer on the other side of the heterojunction.

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 method for producing a neutron detector component (1) comprising a neutron detecting boron carbide layer (2) comprising boron-10 arranged on a substantially neutron transparent substrate (3) is provided. The neutron detecting boron carbide layer (2) comprises boron-10 to a desired thickness (t), and wherein the boron-10 content of the neutron detecting boron carbide layer (2) is at least about 60 at. %.

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 method for measuring the neutron flux in the core of a nuclear reactor, the method including several steps recurrently performed at instants separated by a period, the method comprising at each given instant the following steps: acquiring a total signal by a cobalt neutron detector placed inside the core of the reactor; assessing a calibration factor representative of the delayed component of the total signal due to the presence of cobalt 60 in the neutron detector; assessing a corrected signal representative of the neutron flux at the detector from the total signal and from the calibration factor; assessing a slope representative of the time-dependent change of the calibration factor between the preceding instant and the given instant; the calibration factor at the given instant being assessed as a function of the calibration factor assessed at the preceding instant, of the slope, and of the time period separating the given instant from the preceding instant.

Abstract: Three-dimensional boron particle loaded thermal neutron detectors utilize neutron sensitive conversion materials in the form of nano-powders and micro-sized particles, as opposed to thin films, suspensions, paraffin, etc. More specifically, methods to infiltrate, intersperse and embed the neutron nano-powders to form two-dimensional and/or three-dimensional charge sensitive platforms are specified. The use of nano-powders enables conformal contact with the entire charge-collecting structure regardless of its shape or configuration.

Abstract: A radiation detection system can include a photosensor to receive light from a scintillator via an input and to send an electrical pulse at an output in response to receiving the light. The radiation detection system can also include a pulse analyzer that can determine whether the electrical pulse corresponds to a neutron-induced pulse, based on a ratio of an integral of a particular portion of the electrical pulse to an integral of a combination of a decay portion and a rise portion of the electrical pulse. Each of the integrals can be integrated over time. In a particular embodiment, the pulse analyzer can be configured to compare the ratio with a predetermined value and to identify the electrical pulse as a neutron-induced pulse when the ratio is at least the predetermined value.

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: The present invention provides a boron-containing gas film fast-neutron detector. The fast-neutron detector comprises a package piece having a hollow cavity; a plastic scintillator array provided in the cavity and comprising a plurality of plastic scintillator units, a gap existing between adjacent plastic scintillator units; and a boron-containing gas filled into and gas-tightly sealed in the hollow cavity, the boron-containing gas forming a boron-containing gas film in the gap between the adjacent plastic scintillator units. The fast-neutron detector of the present invention completely does not require use of scarce and expensive 3He gas, nor needs a complicated boron film coating process, improves credibility of signal coincidence, and is adapted for measurement of environment background neutrons and extensively adapted for detection of radioactive substance at sites such as customs ports, harbors and the like.