Abstract: A device for detecting neutrons with an ionization chamber and with optical transduction includes a plurality of optical cavities, each cavity accommodating the free end of an optical fiber and having at least one inner wall coated at least partially with at least one active material. The optical cavities are filled with a gas that can be ionized by an ion arising from the reaction between a neutron and the active material. Each optical cavity is delimited by a cylinder that is closed at its longitudinal ends by a closing disk, the lateral inner wall of which is coated at least partially with an active material. The cylinders adjoin one another while being centered on the longitudinal axis. At least one of the cylinders is pierced laterally with an opening configured to allow through one of the optical fibers whose free end is accommodated in an adjacent cavity.

Abstract: The present invention discloses a scintillator structure and to a method for producing an output optical signal at a specific wavelength range. The scintillator structure comprises a multilayer nanostructure formed by at least one pair of alternating first and second layered material being arranged along one or more principal axes. The multi-layer nanostructure defines predetermined geometrical parameters and the structure is made of at least two different material compositions. At least one of the first layered material, the second layered material, or the combination of both, define scintillation properties. The invention also discloses a detector system for detecting an input radiation comprising a scintillator structure being as defined above and being configured and operable to collect most of the emitted optical signal.

Abstract: The present application relates to a detection structure for fast neutrons and a method for acquiring a neutron energy spectrum, the detection structure for fast neutrons comprises seven semiconductor detection units and a conversion layer made of a hydrogen-containing material, the seven semiconductor detection units comprise a first, a second, a third, a fourth, a fifth, a sixth and a seventh semiconductor detection unit arranged sequentially, the first, the fourth and the seventh semiconductor detection unit constitute an anticoincidence detection group, the second and the third semiconductor detection unit constitute a neutral particle background detection group, the fifth and the sixth semiconductor detection unit constitute a recoil proton detection group, the conversion layer is disposed between the fourth and the fifth semiconductor detection unit, incident neutrons collision with hydrogen atomic nuclei and generate the recoil protons.

Abstract: A scintillator-based imaging screen technology that is sensitive to neutral and charged particles is disclosed. These teachings improve the temporal and spatial resolution limitations of the screens currently used in static and dynamic neutron detection and imaging, neutron tomography, and other advanced neutron imaging equipment used to study materials, such as neutron reflectometers and diffractometers.

Abstract: The present invention relates to an apparatus for determining the location of a radiation source. The apparatus for determining the location of a radiation source according to the present invention comprises: a collimator part for selectively passing radiation therethrough according to the direction in which the radiation is incident; a scintillator part for converting the radiation incident from the collimator part into a light ray; a first optical sensor for converting the light ray incident from one end of the scintillator part into a first optical signal; a second optical sensor for converting the light ray incident from the other end of the scintillator part into a second optical signal; and a location information acquisition part for acquiring information on the location where the light ray is generated in the scintillator part, by using the second optical signal and the second optical signal.

Abstract: A method for joint measuring argon-argon age and cosmic ray exposure age of an extraterrestrial sample is provided. The method for joint measuring determining argon age and cosmic ray exposure age may include: step A, sample packaging; step B, placing the packaged samples into a neutron reactor for irradiation; and step C, determining Ar isotopes of the packaged samples after being performed with a neutron irradiation and thereby calculating argon-argon age and cosmic ray exposure age. The method can overcome the defects of the prior art, and achieve high-precision simultaneous determination of the argon-argon age and the cosmic ray exposure age of samples.

Abstract: A method of measurement of both gamma radiation and neutrons with energies above 500 keV is provided utilizing a scintillation crystal. The method includes allowing gamma quanta and neutrons to interact with the scintillation crystal, collecting light emitted by the scintillation crystal and letting that light interact with a photo detector, and amplifying the signal output. The method then digitizes the amplifier output signal, determines a charge collection time for each interaction measured, determining light decay times, separating signals with distinct decay times, determining a total charge collected from signals with the distinct decay times, and sorting charge signals in a spectrum. The method then counts signals with a second decay time and determines a count rate.

Abstract: A radiation detector includes a printed circuit board and a detector assembly operably connected to the printed circuit board. The detector assembly includes a silicon photomultiplier and an organic scintillator coating applied to a surface of the silicon photomultiplier. A reflective foil covers the organic scintillator coating. A light sealing cover is secured to the printed circuit board such that the silicon photomultiplier and the organic scintillator are encapsulated within the light sealing cover.

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: A combined scintillation crystal includes: at least one scintillation crystal A module and a scintillation crystal B module. The scintillation crystal A module and the scintillation crystal B module are scintillation crystal modules with different performances. The scintillation crystal A module comprises at least one scintillation crystal A, and the scintillation crystal B module comprises at least one scintillation crystal B. The sensitivity of the scintillation crystal A is lower than the sensitivity of the scintillation crystal B, and the light output ability of the scintillation crystal A is higher than the light output ability of the scintillation crystal B. The scintillation crystal B module includes a ray incidence plane for receiving rays, and the at least one scintillation crystal module A is arranged at the outer side of the ray incidence plane of the scintillation crystal B module.

Abstract: A neutron spectrometer is provided to distinguish neutron capture events from other types of radiation in order to measure the energy associated with neutrons in a mixed radiation environment. The neutron spectrometer can include a neutron detector to capture neutrons and a controller to determine the energy associated with the captured neutrons. The neutron detector can include scintillating glass fibers embedded in a plastic scintillator. A photomultiplier tube can be positioned on each end of the detector to detect light pulses generated by both the scintillating glass fibers and the plastic scintillator. A controller can analyze the detected light pulses to determine when a neutron is captured and the energy associated with the neutron capture event.

Abstract: To address the shortcomings presented in the prior art, the present invention provides a system and method to provide improved irrigation management through the detection of fast neutrons. According to a preferred embodiment, the fast neutron detector of the present invention includes a 4-He based noble gas detector, a power source, a signal processing circuit, and a resistor in series with a preamplifier and a shaping amplifier to produce a processed signal. According to a further preferred embodiment, the present invention preferably further includes a signal channel analyzer and a pulse counter/rate meter. According to a further preferred embodiment, the present invention includes a controller which receives a count of detected fast neutrons and translates the detected number of fast neutrons into an irrigation map indicating the required levels of irrigation needed for selected areas of a given field based on the detected moisture levels.

Abstract: A system discriminating fissile material from nonfissile material wherein a digital data acquisition unit collects data at high rate, and processes large volumes of data directly to count neutrons from the unknown source and detect excess grouped neutrons to identify fission. The system includes a Poisson neutron generator for in-beam interrogation of a possible fissile neutron source and inducing neutron emission therefrom, and a DC power supply that exhibits electrical ripple of less than one part per million. A neutron count histogram and Poisson count distribution are overlaid to provide a visual indication of the difference in correlation of natural and induced emitted neutrons from the radiation source to characterize the neutron source as fissile material or non-fissile material.

Abstract: A phoswich neutron detection system with at least two scintillators, each having differing pulse shape characteristics, and an optical detector, and neutron spectroscopy capability.

Abstract: A 3Helium gas counter comprising a container, a gas tube within the container, and a mixture of 3Helium and Xenon or a mixture of 3Helium and Krypton. A method of making a 3Helium gas counter comprising providing a container, placing a gas tube within the container, and depositing a mixture of 3Helium and Xenon or a mixture of 3Helium and Krypton into the gas tube.

Abstract: An apparatus for used in a directional-neutron detector is disclosed. The apparatus comprises a structure having a plurality of parallel active channels separated by inactive regions. The plurality of active channels is filled with scintillating material. The scintillating material is configured to emit light in response to neutron scattering. The scintillating material may be neutron-gamma discriminating. The scintillating material may be sealed in the plurality of active channels. The seal is disposed on respective ends of the plurality of active channels. Directional-neutron detectors are also disclosed having the structure.

Abstract: A method of manufacturing an electron multiplier body, the method includes a step of preparing a first plate-like member having a surface and a back surface and a pair of second plate-like members, a step of forming, in the first plate-like member, a hole portion reaching from the front surface to the back surface, a step of constituting a laminated body by laminating the first and second plate-like members on each other so that the first plate-like member is interposed between the pair of second plate-like members to form a channel defined by the hole portion in the laminated body, a step of integrating the laminated body, a step of constituting a main body portion by cutting the integrated laminated body so that the channel is open, and a step of forming a resistive layer and a secondary electron multiplication layer on an inner surface of the channel.

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: The present invention aims at providing a scintillator for high temperature environments which has satisfactory light emission characteristics under high temperature environments; and a method for measuring radiation under high temperature environments. The scintillator for high temperature environments comprises a colquiriite-type crystal represented by the chemical formula LiM1M2X6 (where M1 is at least one alkaline earth metal element selected from Mg, Ca, Sr and Ba, M2 is at least one metal element selected from Al, Ga and Sc, and X is at least one halogen element selected from F, Cl, Br and I), for example, typified by LiCaAlF6, and the crystal optionally containing a lanthanoid element such as Ce or Eu. The method for measuring radiation under high temperature environments uses the scintillator.

Abstract: A scintillator stack includes a light-transportation layer and a scintillator layer. The scintillator stack can be included in a scintillator device. The scintillator stack can be made using a co-extrusion method.

Abstract: A radiation detector can include both an upper-level and a low-level discriminator. Pulses with amplitudes below a lower pre-selected value will be discarded as noise by the low-level discriminator. Only pulses with amplitudes at or above the lower pre-selected amplitude but at or below a second higher pre-selected value will be subjected to PSD to distinguish between pulses corresponding to neutrons and pulses corresponding to gamma rays. Pulses with amplitudes above the second higher pre-selected value of the upper-level discriminator will be counted as neutron or ionic particle pulses without subjecting these pulses to any PSD.

Abstract: An energy-sensitive imaging detector for fast-neutrons includes energy-selective radiator foil stacks converting neutrons into recoil protons. The foils are separated by gas-filled gaps and formed of two interconnected layers: a hydrogen-rich layer such as a polyethylene layer for neutron-to-proton conversion, and a metal foil layer, such as an aluminum layer, defining a proton energy cut-off and limiting a proton emission angle. Energetic recoil protons emerging from the radiator foil release electrons in surrounding gas in the gaps. An electric field efficiently drifts the electrons through the gaps. An electron detector with position sensitive readout, based on Micro-Pattern Gaseous Detector technologies (such as THick Gaseous Electron Multipliers—THGEM) or other measures provides electron amplification in gas. The charge detector has a dedicated imaging data-acquisition system detecting the drifted electrons thereby sensing the position of the original impinging neutrons.

Abstract: An imaging system includes a magnetic resonance portion that produces an electric field and a second imaging portion, including a detector with a two dimensional array of detector tiles, wherein adjacent tiles along an axial direction are spaced apart by an electrically conductive material, which shields the tiles from the electric field. An imaging system includes a first imaging portion having a detector, which includes an array of scintillation crystals and a photo-sensor coupled to the array of scintillation crystals, wherein an output of the photo-sensor includes a unique ratio of information that identifies each crystal.

Abstract: The present specification describes systems and methods for the simultaneous detection of radioactive materials such as neutrons, muons and gamma rays based on thin gap chamber technology. A thin-gap chamber (TGC) is disclosed having a thermal neutron absorber material, such as 10B4C or 10B8C, which interacts with neutrons to emit heavy particles. The heavy particles, in turn, interact with the gas present in chamber to produce ionization that is converted into a measurable signal. The TGC is embedded in a neutron moderating medium. The detector systems are fabricated from commercially available construction materials and are easy to manufacture at a reasonable cost when compared to conventional He-3 neutron detector systems.

Abstract: The present invention provides a gamma-neutron detector based on mixtures of thermal neutron absorbers that produce heavy-particle emission following thermal capture. In one configuration, B-10 based detector is used in a parallel electrode plate geometry that integrates neutron moderating sheets, such as polyethylene, on the back of the electrode plates to thermalize the neutrons and then detect them with high efficiency. The moderator can also be replaced with plastic scintillator sheets viewed with a large area photomultiplier tube to detect gamma-rays as well. The detector can be used in several scanning configurations including portal, drive-through, drive-by, handheld and backpack, etc.

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 device having: a scintillator material, an optically transparent element containing a glass or polymer and gadolinium oxide, and one or more photomultiplier tubes adjacent to the scintillator material. The optically transparent element is surrounded by the scintillator material.

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

Abstract: A 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: Provided is a scintillation neutron detector capable of measuring neutrons with precision even under a high amount of ? rays as background noise and excellent in neutron counting precision, the scintillation neutron detector comprising a neutron scintillator crystal containing 6Li, and the crystal having a specific surface area of no less than 60 cm2/cm3.

Abstract: The present invention discloses a detector. The detector includes a detector crystal, configured to detect incident rays therein; a plurality of moderator layers, configured to moderate neutrons entering the moderator layer; and a plurality of converter layers, configured to react with said moderated neutrons. The moderator layers and the converter layers are overlapped with each other, and the moderator layers and the converter layers are located outside the detector crystal.

Abstract: A radiation detector can include a solid organic/plastic scintillator that enables neutron and gamma interactions to be readily distinguished via pulse-shape discrimination. Embodiments make use of a scintillator including a polymer matrix with a dispersed scintillation material exhibiting thermally activated delayed fluorescence. The scintillation material can include an organic luminescent material that is free of heavy metals and in which excited triplet states are efficiently promoted into excited singlet states by thermal energy, the excited singlet states then generating a delayed fluorescence when decaying to ground state. As a result, the scintillation material, when exposed to ionizing radiation, can produce a combination of prompt and delayed fluorescence sufficient to enable neutron and gamma interactions to be readily distinguished via pulse-shape discrimination techniques.

Abstract: A simple method of making robust radiation sensor cables using a special fiber cap that holds a scintillating fiber therein directly abutting an end of a fiber optic cable, thus providing a clean and protected connection therebetween.

Abstract: A detection device includes a photon sensor and a scintillator device optically coupled to the photon sensor. The scintillator device includes a scintillator material having a first refractive index, a first refractive material in a first annular space around the scintillator material, and a second refractive material in a second annular space around the first annular space. The first refractive material has a second refractive index. The second refractive index is less than the first refractive index. The second refractive material has a third refractive index. The third refractive index is less than the second refractive index.

Abstract: A neutron detector is disclosed that includes a generally elongate sealed housing. A scintillator based neutron detection assembly is positioned within the elongate housing. The scintillator based neutron detection assembly includes a reflective portion, a plurality of optical fibers, and a scintillator portion. A fiber guide is connected with an end of said scintillator based neutron detection assembly and an end of the at least one bundle of fibers from the plurality of optical fibers is positioned in an output port in the fiber guide. A sensor assembly is included and is connected with the end of the bundle of fibers. An output connector is located on a front end of the generally elongate sealed housing for transmitting an output voltage in response to a neutron event.

Abstract: A radiation detection apparatus can include a semi-cylindrical radiation sensor having a corresponding radiation sensing region, and a photosensor that is optically coupled to the radiation sensor.

Abstract: The present invention discloses a detector. The detector includes a detector crystal, configured to detect incident rays therein; a plurality of moderator layers, configured to moderate neutrons entering the moderator layer; and a plurality of converter layers, configured to react with said moderated neutrons. The moderator layers and the converter layers are overlapped with each other, and the moderator layers and the converter layers are located outside the detector crystal.

Abstract: The invention relates to an improved method for detecting and possibly identifying and/or characterizing nuclear and/or radiological material in a container, vehicle, or on a person, comprising the steps of: a. providing at least one detector, which is capable of detecting radiation events being interrelated to nuclear or radiological material; b. bringing the at least one detector in the vicinity of the container, vehicle or person to be monitored; c. detecting radiation events being interrelated to the container, vehicle or person to be monitored; d. assigning each detected radiation event an individual time stamp in order to generate a time pattern of the detected radiation events; and e. analyzing the time pattern with respect to time correlation structures in order to identify a presence and/or characteristics of the nuclear or radiological material.

Abstract: Various embodiments of the present invention provide a method of detecting inaccessible radiation sources by measuring corresponding ions and excited molecules created by radiation, using LIDAR technology. The LIDAR system of the present invention employs a pulsed laser transmitter, a telescope receiver, and associated control and acquisition systems. Light propagates out from the laser transmitted and is directed into the volume surrounding the radioactive source, or the “ion cloud.” The ion cloud absorbs the transmitted light, which induces the non-fluorescing ions to fluoresce. Light from the ion cloud is then backscattered and the telescope receiver subsequently collects the photons from the backscattered light. The intensity of the fluorescence (determined by the photon count) is measured, which provides an indication of the number density of the ionized atoms. Algorithms can then be used to relate the measured ionization rates to the source activity.

Abstract: A duplex plastic optical fiber may be used to create a dual detector system, which allows for the detection of two distinct areas of radiation in a single sensor cable device. A fiber cap holds a scintillating fiber and slides over an exposed portion of an optical fiber adjacent to an end of the optical fiber to create a concentric connection for a radiation sensor cable used in medical radiation therapy.

Abstract: An organic crystal according to one embodiment includes an organic crystal comprising diphenylacetylene and stilbene or a stilbene derivative, the crystal having physical characteristics of formation from solution, the organic crystal exhibiting a signal response signature for neutrons from a radioactive source. A system according to one embodiment includes an organic crystal comprising diphenylacetylene and stilbene or a stilbene derivative, the crystal having physical characteristics of formation from solution, the organic crystal exhibiting a signal response signature for neutrons from a radioactive source; and a photodetector for detecting the signal response of the organic crystal. Methods of making such crystals are also provided.

Abstract: A radiation detection system can include a scintillator that is capable of emitting scintillating light in response to capturing different types of targeted radiation, a photosensor optically coupled to the scintillator, and a control module electrically coupled to the photosensor. The control module can be configured to analyze state information of the radiation detection system, and select a first technique to determine which type of targeted radiation is captured by the scintillator, wherein the first technique is a particular technique of a plurality of techniques to determine which type of targeted radiation was captured by the scintillator, and the selection is based at least in part on the analysis. In an embodiment, the radiation detection system can be used to change from one technique to another in real time or near real time to allow the radiation detection system to respond to changing conditions.

Abstract: The various technologies presented herein relate to detecting nuclear material at a large stand-off distance. An imaging system is presented which can detect nuclear material by utilizing time encoded imaging relating to maximum and minimum radiation particle counts rates. The imaging system is integrated with a data acquisition system that can utilize variations in photon pulse shape to discriminate between neutron and gamma-ray interactions. Modulation in the detected neutron count rates as a function of the angular orientation of the detector due to attenuation of neighboring detectors is utilized to reconstruct the neutron source distribution over 360 degrees around the imaging system. Neutrons (e.g.

Abstract: Scintillator compositions are provided which include a solvent or matrix containing a fluorophore having the formula (I) and/or a fluorophore having the formula (II), wherein R1 and R2, being identical or different, are independently chosen from the group consisting of hydrogen, halogen, alkyl which optionally contains one or more heteroatoms, alkoxy, aryl and alkyne with an aryl end group; R3 is chosen from the group consisting of hydrogen, alkyl which optionally contains one or more heteroatoms, aryl, heterocycle, ether and ester; R4 and R5, being identical or different, are independently chosen from the group consisting of hydrogen, alkyl which optionally contains one or more heteroatoms, aryl, heterocycle, ether and ester, whereby the R4 and R5 groups are optionally combined to one cyclic structure; and R6, if present, is chosen from the group consisting of hydrogen, aryl and alkyl.

Abstract: An enhanced neutron sensing device, that couples a gadolinium based scintillator with at least two wide bandgap photodiodes to achieve a high sensitivity, low power, and portable neutron detector with high gamma discrimination. Once coupled with electrical signal processing and read-out electrons, the device will output the incident neutron flux in the environment and can be used in locations with known sources of neutrons or for identifying clandestine nuclear materials.

Abstract: Embodiments utilize high energy particles generated by nuclear reactions involving neutron radiation and neutron-sensitive materials to generate and maintain an electric potential gradient between an electrode and a region separated from the electrode by an electric insulator. System and methods contemplated by the invention thereby enable passive detection of neutrons without an externally applied electric potential bias by maintaining a charge accumulation facilitated by nuclear reactions involving neutrons. The charge accumulation produces an electric potential gradient within an electric insulator that separates the charge accumulation from an exterior region.

Abstract: A mixed organic crystal according to one embodiment includes a single mixed crystal having two compounds with different bandgap energies, the organic crystal having a physical property of exhibiting a signal response signature for neutrons from a radioactive source, wherein the signal response signature does not include a significantly-delayed luminescence characteristic of neutrons interacting with the organic crystal relative to a luminescence characteristic of gamma rays interacting with the organic crystal. According to one embodiment, an organic crystal includes bibenzyl and stilbene or a stilbene derivative, the organic crystal having a physical property of exhibiting a signal response signature for neutrons from a radioactive source.

Abstract: The present invention is a radially symmetric imaging detector that measures an incident neutron's or gamma-ray's energy and identifies its source on an event-by-event basis.

Abstract: Embodiments of the present invention can include radiological material detector having a convertor material that emits one or more photons in response to a capture of a neutron emitted by a radiological material; a photon detector arranged around the convertor material and that produces an electrical signal in response to a receipt of a photon; and a processor connected to the photon detector, the processor configured to determine the presence of a radiological material in response to a predetermined signature of the electrical signal produced at the photon detector. One or more detectors described herein can be integrated into a detection system that is suited for use in port monitoring, treaty compliance, and radiological material management activities.

Abstract: A neutron detector without 3He gas, provided with a translucent type plate neutron scintillator having the structure capable to emit fluorescence from double-sides; the neutron scintillator is composed of ZnS fluorescent substance and a neutron converter which contains 6Li or 10B, and arranged at an angle of 45 degrees from the neutrons which are incident in parallel all together, inside of a cylindrical detector housing with the circular or square section where the specular reflector with the reflectance of 90% or more is arranged internally, and the fluorescence emitted when the neutron enters the scintillator is detected by two photo multipliers arranged on both sides, and signals output from these two photo multipliers are processed to be taken out as a neutron signal.