Abstract: A silicon-on-insulator (SOI) neutron detector comprising a silicon-on-insulator structure, wherein the silicon-on-insulator structure consists of an active semiconductor layer, a buried layer, and a handle substrate, a lateral carrier transport and collection detector structure within the active semiconductor layer of the silicon-on-insulator structure, and a neutron to high energy particle converter layer on the active semiconductor layer.

Abstract: A multi-stage process utilizes one or more sensors, including radiation sensors, on a distributed network for the detection and identification of radiation, explosives, and unauthorized hazardous materials within a shipping container. The sensors can be configured as nodes on the network. The system collects data, such as radiation data, from one or more sensors. The system spectrally analyzes the collected radiation data. The system identifies one or more isotopes based on the spectrally analyzed radiation data. A central monitoring station can monitor radiation data received from the sensors. Communication of sensor data can be done using TCP/IP communication over the network.

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

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

Abstract: A system for detecting explosive materials includes at least one deuterium/tritium neutron generator module, at least one germanium detector module, and an analysis module. The deuterium/tritium neutron generator module bombards an object with neutrons. The germanium detector module detects gamma rays emitted by the object in response to the neutrons. The analysis module analyzes the gamma rays detected by the germanium detector module for the presence of explosive materials on or within the object.

Abstract: A neutron detection device (100) includes a semiconductor substrate including a gallium arsenide substrate region (102) having a back surface, and a high purity gallium arsenide active region (104) having a front surface. A back contact layer (118) is disposed on the back surface for providing a first voltage potential at the back surface. Elongated tube cavities extend from respective openings in the front surface into the active region (104) and almost through, but not totally through, the active region. A front contact layer is disposed on the front surface for providing a second voltage potential at the front surface. Neutron reactive material, e.g., pulverized Boron-10 powder, fills the elongated tube cavities to a high packing density. Optionally, spherical holes are formed into the substrate. The spherical holes are filled with neutron reactive material to enhance the efficiency of the neutron detection device.

Abstract: Neutron detectors including one or more gamma shields over memory dies and methods of making the neutron detectors are provided. The neutron detectors can contain two or more memory dies, neutron-reactant layers over the two or more memory dies, and one or more gamma shields over at least a portion of or an entire of the two or more memory dies. By containing the gamma shield over the at least a portion of or an entire of the two or more memory dies, the neutron detector can detect and discriminate neutrons in the presence of gamma rays.

Abstract: A method includes detecting a neutron based on a time proximity of a first signal and a second signal. The first signal indicates detection of at least one of a neutron and a gamma ray. The second signal indicates detection of a gamma ray. The method further includes measuring an amount of detected gamma rays, for example, an amount different from an amount detected and associated with the second signal.

Abstract: A radiation detection blanket for use in surveying a broad or irregular area of interest for radiation emissions. Small radiation detectors are affixed to the fabric and distributed relative to its surface area. The detector materials may be of the OSL, TLD, or ERD variety, or may be a combination of OSL, TLD and ERD. Detector materials having varying thicknesses of high Z coatings may be clustered together in the blanket fabric to yield a gamma radiation spectrum. Use of a converter material on the detector material allows the blanket to detect neutron radiation. The blanket includes specialized transmission means for allowing the detector materials to be read individually, by passing the reader along a surface or along an edge of the blanket. A composite radiation measurement is obtained upon reading the individual detectors, allowing determination of the radiation distribution within the object being surveyed by the blanket.

Abstract: A solid-state detector for detection of neutron and alpha particles detector and methods for manufacturing and use thereof are described. The detector has an active region formed of a polycrystalline semiconductor compound comprising a particulate semiconductor material sensitive to neutron and alpha particles radiation imbedded in a binder. The particulate semiconductor material contains at least one element sensitive to neutron and alpha particles radiation, selected from a group including 10Boron, 6Lithium, 113Cadmium, 157Gadolinium and 199Mercury. The semiconductor compound is sandwiched between an electrode assembly configured to detect the neutron and alpha particles interacting with the bulk of the active region. The binder can be either an organic polymer binder or inorganic binder. The organic polymer binder comprises at least one polymer that can be selected from the group comprising polystyrene, polypropylene, Humiseal™ and Nylon-6.

Abstract: A neutron detection structure built from a Silicon-On-Insulator memory cell includes a conversion layer for converting incident neutrons into emitted charged particles, a device layer for receiving the emitted charged particles, a buried oxide layer separating the conversion layer from the device layer and directly adjacent to the conversion layer and the device layer, an isolation layer, a passivation layer formed on the isolation layer opposite the device layer and buried oxide layer, a carrier adhered by an adhesion layer to the passivation layer opposite the isolation layer, and a plurality of conductive contacts to provide electrical contact to the device layer.

Abstract: A system, method, and floating intelligent perimeter sensor, provide protection for waterways and critical infrastructures. The system and method utilize one or more floating intelligent perimeter sensors to detect, and in some cases identify, hazardous materials associated with vessels in the waterways. The hazardous materials detected, and optionally identified, can include radiological materials, fissile materials, explosives, chemicals and biological materials (CBRNE). A set of radiation data associated with a radiation source in a vessel is received from the one or more floating intelligent perimeter sensors. At least one histogram is generated based on the set of radiation data. The at least one histogram is compared to multiple spectral images associated with known materials. The at least one histogram is determined to substantially match at least one of the multiple spectral images. A determination is made whether a material associated with the radiation source is a hazardous material.

Abstract: A system and method determine a direction associated with gamma and/or neutron radiation emissions. A first radiation photon count associated with a first detector in a detector set is received from the first detector. The first radiation photon count is associated with at least one radiation source. A second radiation photon count associated with a second detector in the detector set is received from the second detector. The first radiation photon count is compared to the second radiation photon count. One of the first detector and the second detector is identified to have detected a larger number of radiation photons than the other. The at least one radiation source is determined to be substantially in a direction in which the one of the first detector and the second detector that has detected the larger number of radiation photons is facing.

Abstract: An integrated radiation detector having a pulse-mode operating photosensor optically coupled to a gamma sensing element and a neutron sensing element is disclosed. The detector includes pulse shape and processing electronics package that uses an analog to digital converter (ADC) and a charge to digital converter (QDC) to determine scintillation decay times and classify radiation interactions by radiation type. The pulse shape and processing electronics package determines a maximum gamma energy from the spectrum associated with gamma rays detected by the gamma sensing element to adaptively select a gamma threshold for the neutron sensing element. A light pulse attributed to the neutron sensing element is a valid neutron event when the amplitude of the light pulse is above the gamma threshold.

Abstract: A method and apparatus for the remote, non-invasive detection or characterization of materials manifests a controlled temperature perturbation to the sample material location concurrently with sample interrogation by ionizing radiation and with detection of the response emission energy spectra. This configuration induces and detects Doppler effects manifested at the sample location, allowing material inventory and composition measurements, and allowing a comparative reduction of the exposure duration compared to other isothermal proportional count, coincidence count or spectral analysis techniques. The method and apparatus apply primarily to the detection of elements and isotopes in baggage handling, cargo inspection, chemical characterization, process control and geologic operations, though the method and apparatus are not restricted to these applications.

Abstract: A system for producing beams of high energy photons and neutrons and a method to use such beams to actively interrogate and detect concealed nuclear materials, radiological materials, and chemical explosives.

Abstract: A dosimeter for detecting high-energy neutron radiation having a neutron converter and a detection element is proposed which is characterized by the neutron converter comprising metal atoms which convert the energy of the neutrons into protons, alpha particles and other charged nuclei in a suitable energy range so that they are detectable.

Abstract: A photon generating event capture system is configured to capture light photons. Image intensifiers are arranged to amplify light photons and sensors are arranged to capture the amplified light photons. A control system detects the amplification of light photons by the image intensifiers. Upon detecting amplification, the control system deactivates the image intensifiers to shutdown further light photon amplification and switches the sensors from a clear mode to an acquisition mode within a period of time less than a decay time of the image intensifiers. The locations and intensities of the amplified light photons are then captured and read out by the sensors. By operating the sensors in a clear mode prior to detecting amplification of light photons, noise recorded by the sensors prior to the detection of light photon amplification is either shifted out of the sensor prior to the photon generating event or is smeared across the sensor data.

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

Abstract: A neutron detector, and method for fabricating same, having an active layer comprised of organic and inorganic materials such as polymers and/or small molecules. These materials function as a semiconductor host matrix that transports carriers excited by neutron absorption. The active layer is comprised of host semiconductor materials, composites of the host semiconductor materials with other polymers molecules, and particles, or multi-layer structures of the host semiconductor materials with other materials. The host semiconductor materials include in their molecular structure neutron capturing atoms such as 10B, 6Li, 157Gd, 235U, 239Pu, 51V, and 103Rh, or alternatively are blended with molecules or particles that contain the above atoms in addition to electron accepting molecules or particles.

Abstract: A solid-state thermal neutron detector comprises: a layered structure that includes; an electrically insulating substrate; a first electrode affixed to the substrate; a neutron-reactive layer affixed to and in ohmic contact with the first electrode; and a second electrode affixed to and in ohmic contact with the neutron-reactive layer; a voltage source electrically coupled to the first and second electrodes; and an electrical current detector electrically coupled in series between the layered structure and the voltage source.

Abstract: A neutron detection device includes a neutron conversion layer in close proximity to an active semiconductor layer. The device is preferably based on the modification of existing conventional semiconductor memory devices. The device employs a conventional SRAM memory device that includes an SOI substrate. The SOI substrate includes an active semiconductor device layer, a base substrate and an insulating layer between the active semiconductor device layer and the base substrate. The base substrate layer is removed from the memory device by lapping, grinding and/or etching to expose the insulating layer. A neutron conversion layer is then formed on the insulating layer. The close proximity of the neutron conversion layer to the active semiconductor device layer yields substantial improvements in device sensitivity.

Abstract: This invention relates to an apparatus for detecting hydrogeneous material on a ship's deck comprising a neutron source located below the surface of the ship's deck and emitting fast/energy-rich neutrons, and a detector device that is located below the surface of the ship's deck and detecting thermal neutrons. The invention further relates to a corresponding method of detecting hydrogeneous material on a ship's deck. Hereby an apparatus and a method are provided for detecting occurrences of water on a ship's deck, wherein these occurrences appear in particular when travelling in rough weather conditions. The apparatus being located below the ship's deck, it is consequently not exposed to wear due to rough weather conditions.

Abstract: A broad spectrum neutron detector has a thermal neutron sensitive scintillator film interleaved with a hydrogenous thermalizing media. The neutron detector has negligible sensitivity to gamma rays and produces a strong and unambiguous signal for virtually all neutrons that interact with the hydrogenous volume. The interleaving of the layers of thermal neutron sensitive phosphors helps ensure that all parts of the thermalizing volume are highly sensitive.

Abstract: The radiation detector according to this invention has a common electrode for bias voltage application formed on a surface of an amorphous selenium semiconductor film (a-Se semiconductor film) sensitive to radiation. The common electrode is a gold thin film having a thickness in a range of 100 to 1,000 ?. The gold thin film acting as the common electrode may be formed on the surface of the a-Se semiconductor film at a relatively low vapor deposition temperature and in a reduced vapor deposition time. This feature suppresses a generation of defects in the a-Se semiconductor film due to formation of the common electrode. The gold thin film for the common electrode is not so thick as in the prior art, but is 1,000 ? or less. With the reduced thickness, the common electrode has improved boding property with respect to the a-Se semiconductor film.

Abstract: The invention relates to an instrument which uses an individual semi-conductive detector with special coverings as an essential sensor, and a method whereby the amplitude information of the signals from said semi-conductive detector are used to determine a person's dose in mixed neutron/photon-fields. Said instrument is highly sensitive and has a low energy dependency. It is possible for the dose to be read directly, and to emit a warning if the dose limit is exceeded. The inventive method enables a compact person's dose meter, which is immune to interference, to be produced with low power consumption.

Abstract: A ?-conjugated organic material for detecting ionizing radiation, and particularly for detecting low energy fission neutrons. The ?-conjugated materials comprise a class of organic materials whose members are intrinsic semiconducting materials. Included in this class are ?-conjugated polymers, polyaromatic hydrocarbon molecules, and quinolates. Because of their high resistivities (?109 ohm·cm), these ?-conjugated organic materials exhibit very low leakage currents. A device for detecting and measuring ionizing radiation can be made by applying an electric field to a layer of the ?-conjugated polymer material to measure electron/hole pair formation. A layer of the ?-conjugated polymer material can be made by conventional polymer fabrication methods and can be cast into sheets capable of covering large areas. These sheets of polymer radiation detector material can be deposited between flexible electrodes and rolled up to form a radiation detector occupying a small volume but having a large surface area.

Abstract: A system for detecting neutron radiation. A liquid cocktail mixture comprised of a neutron absorber and a scintillator is housed in a Teflon® tube having a mirror at one end of the tube and a windowed portal at the other end of the tube. Neutrons that penetrate the tube react with the neutron absorber producing ionization that excites a scintillator to produce photons. A photo-multiplier tube is coupled with the windowed portal for receiving photons and converting the photons to electrical signals. A processing device is coupled to the photo-multiplier output for receiving and analyzing the electrical signals so as to provide a measurement pertaining to the presence and relative strength of neutron radiation. The tube can be adapted to function as a portable survey instrument. Alternatively, the tube can be stretched to cover large apertured areas. In such implementations a wavelength shifter is employed to convert light emitted to another wavelength giving a multiplier effect necessary for long light guides.

Abstract: A system for measuring a thermal neutron emission from a neutron source is provided. The system employs a detector utilizing a plurality of doped pBN layers, wherein the doped pBN layers are doped with at least one dopant across an a-b plane of the layers for an electrical resistivity of 1014 ohm-cm or less.

Abstract: In detectors for imaging and other applications, delay line anodes are arrayed so as to allow detection of the location and/or timing of particle hits. The anodes are arrayed to provide an upper anode and one or more lower anodes, with particles incident on the upper anode passing in turn to the lower anodes. The anode arrays allow the use of identically manufactured anodes which are maintained in parallel spaced relation along the travel path of the particles of interest without dielectric material or other structure situated between the anodes. The spacing between the anodes is preferably adjustable so as to allow the installer and/or user to modify the performance characteristics of the array. The anodes may be made of pre-formed metal foil signal and ground layers laminated onto opposing sides of a dielectric sheet, or may be etched or otherwise formed from flex circuit material, so that the anodes and the overall array are light weight, compact, and flexible.

Abstract: A neutron detector is provided which is able to measure thermal neutron radiation within a gap filled with a substance that permits scintillation in the absorption of thermal neutron radiation, the gap being formed between at least a first and second spaced apart photodetector working in electrical coincidence. The substance disposed within the gap can be either a gas, liquid or solid. In the case of a gas, a shell is used so that the gas can be retained and kept under pressure. The neutron detector is able to differentiate between gamma radiation and neutron energy. An alternate embodiment of the novel detector includes a device which employs a plurality of detectors surrounding a moderator which can be used to measure both thermal and high energy neutrons.

Abstract: A method and system for measuring neutron emissions and ionizing radiation, such as gamma emissions, solid state detector for use therein, and imaging system and array of such detectors for use therein are provided using Cd- and/or Hg-containing semiconductors or B-based, Li-based or Gd-based semiconductors. The resulting systems and detectors used therein may be not only compact and portable, but also capable of operating at room temperature. The detectors may also be operable as gamma ray spectrometers.

Abstract: A silicon substrate (1) includes a neutron detecting part comprising a 10B diffusion layer which includes boron introduced therein containing isotopes 10B, an &agr;-ray detecting part including a pn junction (13) defined by a p well (11) and an n well (12), and an analytic circuit part for analyzing electric charge generated in the pn junction (13), all of which are provided on a single chip. An &agr;-ray generated in the 10B diffusion layer (10) as a result of entering of neutrons generates electron-hole pairs (16) in a depletion layer of the pn junction (13). The analytic circuit part collects and analyzes electric charge of the electron-hole pairs (16). On the basis of the result of analysis, the volume of neutrons entering into the pn junction (13) is specified.

Abstract: A method and system for measuring neutron emissions and ionizing radiation, such as gamma emissions, solid state detector for use therein, and imaging system and array of such detectors for use therein are provided using Cd- and/or Hg-containing semiconductors or B-based, Li-based or Gd-based semiconductors. The resulting systems and detectors used therein may be not only compact and portable, but also capable of operating at room temperature. The detectors may also be operable as gamma ray spectrometers.

Abstract: A pBN neutron detector and method of forming a pBN neutron detector with the neutron detector formed by depositing multiple layers of pBN having a crystalline lattice structure with its crystallographic ‘c plane’ predominantly parallel to the deposited layers. The neutron detector forms a geometry having two opposite sides aligned parallel to the ‘ab planes’ of the structure and has a thickness of between one micron and one mm between the opposite sides. Metallized contacts are applied to the opposite sides and the detector is oriented relative to a source of neutrons such that the neutrons pass through the volume of the detector and cause electrons to flow in response to alpha particles generated from the interaction of neutrons with the Boron-10 isotope present in pBN.

Abstract: A neutron detection system for detection of contaminants contained within a bulk material during recycling includes at least one neutron generator for neutron bombardment of the bulk material, and at least one gamma ray detector for detection of gamma rays emitted by contaminants within the bulk material. A structure for analyzing gamma ray data is communicably connected to the gamma ray detector, the structure for analyzing gamma ray data adapted. The identity and concentration of contaminants in a bulk material can also be determined. By scanning the neutron beam, discrete locations within the bulk material having contaminants can be identified.

Abstract: A method for determining which of a plurality of detectors transmitted a signal, such as a signal related to neutron or gamma emissions, includes connecting each of the detectors to a single cable, such as an environmentally rugged cable. Signals are transmitted from each of the detectors over the single cable. The two ends of the cable are connected to two receivers. A different unique delay is introduced between receipt by the two receivers of a signal over the cable for each of the detectors. The receivers, which have a preamplifier, an amplifier and a discriminator, receive the signals from the two ends of the cable. A timing analyzer, such as a time-to-amplitude converter, measures a delay between one signal from one end and the other signal from the other end of the cable. A processor employs the amplitude of the signal output by the timing analyzer.

Abstract: A pBN neutron detector and method of forming a pBN neutron detector with the neutron detector formed by depositing multiple layers of pBN having a crystalline lattice structure with its crystallographic ‘c plane’ predominantly parallel to the deposited layers. The neutron detector forms a geometry having two opposite sides aligned parallel to the ‘ab planes’ of the structure and has a thickness of between one micron and one mm between the opposite sides. Metallized contacts are applied to the opposite sides and the detector is oriented relative to a source of neutrons such that the neutrons pass through the volume of the detector and cause electrons to flow in response to alpha particles generated from the interaction of neutrons with the Boron-10 isotope present in pBN.

Abstract: The detection efficiency, or sensitivity, of a neutron detector material such as of Si, SiC, amorphous Si, GaAs, or diamond is substantially increased by forming one or more cavities, or holes, in its surface. A neutron reactive material such as of elemental, or any compound of, 10B, 6Li, 6LiF, U, or Gd is deposited on the surface of the detector material so as to be disposed within the cavities therein. The portions of the neutron reactive material extending into the detector material substantially increase the probability of an energetic neutron reaction product in the form of a charged particle being directed into and detected by the neutron detector material.

Abstract: A device for detecting neutrons includes a semi-insulated bulk semiconductor substrate having opposed polished surfaces. A blocking Schottky contact comprised of a series of metals such as Ti, Pt, Au, Ge, Pd, and Ni is formed on a first polished surface of the semiconductor substrate, while a low resistivity (“ohmic”) contact comprised of metals such as Au, Ge, and Ni is formed on a second, opposed polished surface of the substrate. In one embodiment, n-type low resistivity pinout contacts comprised of an Au/Ge based eutectic alloy or multi-layered Pd/Ge/Ti/Au are also formed on the opposed polished surfaces and in contact with the Schottky and ohmic contacts. Disposed on the Schottky contact is a neutron reactive film, or coating, for detecting neutrons. The coating is comprised of a hydrogen rich polymer, such as a polyolefin or paraffin; lithium or lithium fluoride; or a heavy metal fissionable material.

Abstract: In a method and apparatus for determining neutron spectra using at least two neutron detectors which provide integral counting rates from which the spectrum of a neutron radiation can be approximated, and which consist each of a semiconductor diode, a converter layer, an inactive layer and an active layer. The various layers of each detector are different from those of the other neutron detector and so selected that the sensitivity functions of the two neutron detectors are different. An artificial neutral network is provided which is especially trained and to which the counting rates of the detectors are supplied to be processed for obtaining the neutron spectrum.

Abstract: This invention relates to both the apparatus and method for increasing the sensitivity of measuring the amount of radioactive material in waste by reducing the interference caused by cosmic ray generated neutrons. The apparatus includes: (a) a plurality of neutron detectors, each of the detectors including means for generating a pulse in response to the detection of a neutron; and (b) means, coupled to each of the neutrons detectors, for counting only some of the pulses from each of the detectors, whether cosmic ray or fission generated. The means for counting includes a means that, after counting one of the pulses, vetos the counting of additional pulses for a prescribed period of time. The prescribed period of time is between 50 and 200 &mgr;s. In the preferred embodiment the prescribed period of time is 128 &mgr;s. The veto means can be an electronic circuit which includes a leading edge pulse generator which passes a pulse but blocks any subsequent pulse for a period of between 50 and 200 &mgr;s.

Abstract: Crystals of lithium tetraborate or alpha-barium borate had been found to be neutron detecting materials. The crystals are prepared using known crystal growing techniques, wherein the process does not include the common practice of using a fluxing agent, such as sodium oxide or sodium fluoride, to reduce the melting temperature of the crystalline compound. Crystals prepared by this method can be sliced into thin single or polycrystalline wafers, or ground to a powder and prepared as a sintered compact or a print paste, and then configured with appropriate electronic hardware, in order to function as neutron detectors.

Abstract: A neutron monitoring instrument, principally of the survey type, is provided with an inner neutron detector(s) enclosed in a layer of neutron attenuating material and one or more outer neutron detectors provided on the attenuating layer and enclosed in a layer of neutron moderating material. The inner detector(s) monitor neutrons in the 100 KeV to 15 MeV energy range, with the outer detectors monitoring neutrons in the thermal to 100 KeV range. Sensitivity across the spectrum and evenness of response are improved compared with the prior art to give better close equivalence determinations.

Abstract: A process for making a solid state photoconducting detector from an organic material that has a density very close to that of normal tissue. The resulting detector senses ionizing radiation and has a tissue equivalent response to radiation. The detector's efficiency for any given radiation quality and energy can be measured and the detectors can directly measure dose equivalent. The invention also includes the device itself. The invention encompasses the use of the detector for other purposes such as a solid state photoconducting detector with organic materials unrelated to tissue equivalent properties.

Abstract: Detectors are used to monitor the status of spent nuclear fuel storage containers non-invasively while they remain in storage casks. The detectors measure neutron flux and &ggr;-ray flux and may also measure temperature variations of the spent nuclear fuel. The measurements can be accomplished actively or passively, with minimal exposure of individuals to radiation fields or other hazardous conditions. Preferred neutron and &ggr;-ray detectors have a semiconductor active region that is resistant to neutron damage. Incipient structural failures may also be detected using measurements based on electrical continuity, with data being transmitted to an external pickup coil.