Abstract: A nondestructive inspection apparatus makes a neutron beam incident on an inspection target, detects a specific gamma ray deriving from a target component in the inspection target, among gamma rays generated by the neutron beam, and determines a depth at which the target component exists, based on a result of the detecting. The nondestructive inspection apparatus includes a neutron source that emits a neutron beam to a surface of the inspection target, a gamma ray detection device that detects, as detection intensities, intensities of a plurality of types of specific gamma rays whose energy differs from each other, and a ratio calculation unit that determines a ratio between the detection intensities of a plurality of types of the specific gamma rays.

Abstract: A system and method for performing active scanning on a nuclear fuel rod are provided. The system includes an electrically-driven neutron generator including an ion source, an accelerator, and a target; a moderator surrounding the neutron generator and configured to moderate neutrons generated by the neutron generator; a fuel rod channel disposed within the moderator, the fuel rod channel configured to receive a nuclear fuel rod and subject the nuclear fuel rod to a predetermined neutron flux; and a plurality of radiation detectors. When the nuclear fuel rod is subjected to the predetermined neutron flux, neutrons induce a secondary radiation of prompt and delayed gamma emissions, neutron emission, or a combination thereof that are detected by the plurality of radiation detectors to determine an amount of fissile material in the nuclear fuel rod and a spatial distribution of the fissile material along a length of the nuclear fuel rod.

Abstract: A shielded X-ray radiation apparatus is provided comprising an X-ray source, an X-ray attenuation shield including an elongate cavity to house the X-ray source and incorporating a region to accommodate a sample, a neutron attenuation shield, and a gamma attenuation shield. The neutron attenuation shield is situated adjacent to and substantially surrounds the X-ray attenuation shield and the gamma attenuation shield is adjacent to and substantially surrounds the neutron attenuation shield. In some embodiments a removable sample insertion means is provided to insert samples into the elongate cavity and which is composed of adjacent blocks of material, each respective block having a thickness and a composition which substantially matches the thickness and a composition of one of the X-ray attenuation, neutron attenuation and gamma-ray attenuation shields.

Abstract: Multiple tagged neutrons are emitted from an associated particle imaging neutron generator. The tagged neutrons penetrate a target material and interact with the target material nucleus—which emits nucleus-specific gamma rays. A gamma ray detector detects all gamma rays—including the nucleus-specific gamma rays. An alpha-gamma timing spectrum is constructed for all detected gamma rays. For a specific energy level (MeV) corresponding with the target material nucleus, a peak in the alpha gamma timing spectrum indicates the presence of the target material. Based on the peaking time of the gamma rays (due to tagged neutrons interaction with the target material nucleus) in the alpha-gamma timing spectrum for the specific energy level, the distance from the neutron generator to the target material can be calculated. The nucleus-specific gamma ray spectrum data can be effectively collimated by programming the system to detect the gamma rays in a time window corresponding to the peaking time.

Abstract: A faulted condition determination method is designed to detect a chromium content and a nickel content in a predetermined boundary region proximate to a boundary between a high-strength ferrite steel and a weld material in a welded joint in which the high-strength ferrite steel and another steel are welded together using the weld material containing nickel and to thereby determine the faulted condition of the predetermined boundary region based on the chromium content and the nickel content. Accordingly, it is possible to appropriately determine the faulted condition of welding of a replacement part in which a high-strength ferrite steel and another steel are welded together using a nickel-based weld material.

Abstract: An apparatus and a method for sorting, particularly chopped, aluminum scrap by alloy groups are disclosed, in which the aluminum scrap is separated into fractions, fractions of the aluminum scrap are irradiated by at least one neutron source, the gamma radiation that the individual fraction emits due to this neutron irradiation is detected by at least one detector, and based on this, an energy spectrum associated with the respective fraction is generated, based on which energy spectrum a relative ratio of the weight proportions of at least two alloy elements of this fraction is determined, and based on this relative ratio, this fraction is allocated to its corresponding alloy group, and then the fractions are sorted by the alloy groups to which they have been allocated.

Abstract: The present specification provides a baggage scanning system including: an aperture defining a scanning tunnel; a conveyor moving through the scanning tunnel, a baggage being scanned moving on the conveyor; a UWB radar array surrounding the aperture for providing radar scan data corresponding to the baggage; a LCMD array positioned at a location around the baggage allowing obtaining of LCMD scan data corresponding to the baggage; and at least a processor for correlating the radar scan data and the LCMD scan data for providing one or more suspicious regions highlighted over a video image of the baggage being scanned.

Abstract: The detection and assay of fissionable material is carried out on a container known or suspected to have a material with at least one fissionable isotope. The material is irradiated with neutrons from two or more different neutron sources. The fission rates inducted at each irradiation energy are acquired with at least one neutron detector. A multispectral active neutron interrogation analysis (MANIA) is carried out to compare the detected fission rates of the neutron spectra with calculated fission rates where an iterative algorithm is carried out on a system of linear equations to solve for the isotopic composition of one or more isotopes to determine the presence, identity, and quantities of fissionable isotopes in said container.

Abstract: The present specification discloses an X-ray scanning system with a non-rotating X-ray scanner that generates scanning data defining a tomographic X-ray image of the object and a processor executing programmatic instructions where the executing processor analyzes the scanning data to extract at least one parameter of the tomographic X-ray image and where the processor is configured to determine if the object comprises a liquid, sharp object, narcotic, currency, nuclear materials, cigarettes or fire-arms.

Abstract: The present application is directed toward cargo scanning systems having scanners, each arranged to scan a respective object and generate a set of scan data, processors arranged to process each set of scan data to determine whether it meets a predetermined threat condition, workstations, and data management system arranged to direct data that meets the threat condition to one of the workstations for analysis.

Abstract: A method of discriminating fissile material from non-fissile material with a digital data acquisition system that 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 system according to an exemplary aspect of the present disclosure includes, among other things, a generator-detector configured to be attached to a pipe. The generator-detector is configured to measure the concentration of mercury in the pipe in a non-destructive manner. A method is also disclosed.

Abstract: In accordance with embodiments of the invention, at least the potential presence of Special Nuclear Material (“SNM”) is determined by the detection of prompt neutrons, prompt gamma rays, delayed neutrons, and/or delayed gamma rays from photofission, via time-of-flight (“TOF”) spectroscopic methods. Methods and systems are disclosed.

Abstract: A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly to count neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a Poisson neutron generator for in-beam interrogation of a possible fissile neutron source and a DC power supply that exhibits electrical ripple on the order of less than one part per million. Certain voltage multiplier circuits, such as Cockroft-Walton voltage multipliers, are used to enhance the effective of series resistor-inductor circuits components to reduce the ripple associated with traditional AC rectified, high voltage DC power supplies.

Abstract: An airport baggage handling system is described for transferring baggage between airport passenger stations and aircraft loading zones. The airport baggage handling system includes in-line screening devices including at least one high resolution or high risk screening device and at least one low resolution or low risk screening device. Each piece of checked baggage is provided with a tag including, inter alia, information regarding the security status of the piece of baggage. A computer control system for controlling operation of the baggage handling system uses the information regarding the security status of the piece of baggage to selectively route the piece of baggage through one of the high and low risk scanning devices. In one embodiment, the security status of the baggage is derived from the security status of the passenger associated with the baggage.

Abstract: A device designed to be used for neutron imaging, immersed in a medium containing specimens to be analyzed, comprises a first converter comprising a first material capable of converting thermal neutron radiation into remnant beta radiation and a second converter comprising a second material capable of converting a remnant beta radiation into light radiation, the second converter being in contact with the first converter. A method is also provided for neutron imaging immersed in a medium and using the device.

Abstract: A method for evaluating wellbore conduit condition includes using measurements of at least one of (i) inelastic gamma rays made during emission a burst of neutrons into the conduit from within the conduit at at least one spaced apart location from a position of the emission and (ii) epithermal neutrons or capture gamma rays therefrom detected at at least two spaced apart locations from the position of the emission within a selected time after the emission. The at least one of the measurements of inelastic gamma rays and epithermal neutron or capture gamma ray counts are characterized to estimate an amount of loss of iron in the conduit.

Abstract: One or more systems and/or techniques are provided to identify and/or classify objects of interest (e.g., potential granular objects) from a radiographic examination of the object. Image data of the object is transformed using a spectral transformation, such as a Fourier transformation, to generate image data in a spectral domain. Using the image data in the spectral domain, one or more one-dimensional spectral signatures can be generated and features of the signatures can be extracted and compared to features of one or more known objects. If one or more features of the signatures correspond (e.g., within a predetermined tolerance) to the features of a known object to which the feature(s) is compared, the object of interest may be identified and/or classified based upon the correspondence.

Abstract: The present invention is directed to a system for screening the content of the air proximate to a target for the presence of one or more illicit substances by using a chemical detector, a metal detector and a radiation detector all houses within a portable detection unit that may be carried by hand to detect threat substances on a target. The system also comprises a support module that is coupled either wirelessly or though a conduit to the portable detection unit to support the operations of the portable detection unit by proving processing and analysis of the detected results and power. The system also comprises a vacuum source for drawing air proximate to the target into the portable detection unit for vaporization and analysis. The vacuum source may be within the support module and drawing air through a hose in the conduit, or may be within the portable detection unit itself.

Abstract: A system for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causing fission (n, f) reactions in U-238. The U-238 can be deployed as layers sandwiched between layers of neutron-reflecting material, or as rods surrounded by neutron-reflecting material.

Abstract: Apparatus and methods for determining the absence or presence of contraband in an object with a fast neutron source for irradiating the object; a detector for measuring ?-rays emitted by the irradiated object from energy state relaxation as a result of neutron capture, typically after the object has been irradiated.

Abstract: A system for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causing fission (n, f) reactions in U-238. The U-238 can be deployed as one or more layers sandwiched between layers of neutron-reflecting material, or as rods surrounded by neutron-reflecting material. The gaseous fission products can be withdrawn from the irradiation chamber on a continuous basis, and the radioactive iodine isotopes (including I-131) extracted.

Abstract: A neutron detector system and method for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. Comparison of the observed neutron count distribution with a Poisson distribution is performed to distinguish fissile material from non-fissile material.

Abstract: Target assemblies are provided that can include a uranium-comprising annulus. The assemblies can include target material consisting essentially of non-uranium material within the volume of the annulus. Reactors are disclosed that can include one or more discrete zones configured to receive target material. At least one uranium-comprising annulus can be within one or more of the zones. Methods for producing isotopes within target material are also disclosed, with the methods including providing neutrons to target material within a uranium-comprising annulus. Methods for modifying materials within target material are disclosed as well as are methods for characterizing material within a target material.

Abstract: Apparatus for generating thermal neutrons includes an electron accelerator for generating an electron beam and a converter for converting the electron beam into photons. A receiving device is provided for receiving the photons and includes a material which provides a photoneutron target for the photons, for producing high energy neutrons in a photonuclear reaction between the photons and the photoneutron target, and for moderating the high energy neutrons to generate the thermal neutrons. The electron beam has an energy level high enough to produce photons of sufficient energy to exceed the photodissociation threshold of the selected target material, but that is sufficiently low as to enable the material to moderate the high energy neutrons resulting from the photonuclear reaction.

Abstract: A method for the non-destructive elemental analysis of large-volume samples using neutron radiation and a device for carrying out the method. In the method, the sample is irradiated with fast neutrons in a pulsed manner and the gamma radiation emitted by the sample is measured. The quantity of an element contained in the sample is evaluated after the background signal is subtracted from the area of the photopeak caused by the element in a plot of count rate versus energy. The gamma radiation emitted by a subregion of the sample, the composition of which is known, is evaluated in order to determine the neutron flux at the location of the sample. A metallic enclosure of the sample, such as a standardized waste container, can be selected as such a subregion, for example. A novel evaluation method based on multiparameter analysis can quantify, on the basis thereof, the presence of individual elements more quickly and more accurately than is possible according to the previous prior art.

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

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

Abstract: A method and a system for fissile content measurement that utilizes a detector configured to detect fast neutrons. An external radiation source may be used to induce fission in a sample to allow the measurement of a fissile material of the sample with a low spontaneous fission probability. Analyzing the sample may be based on the energy spectrum of emitted neutrons. That is, the energy information regarding the energy of the fast neutrons is obtained, and the fast neutrons as having a high likelihood of originating in a nuclear fission process as opposed to originating in an (alpha,n) reaction by utilizing the obtained energy information are classified to analyze the sample. Alternatively, a position of interaction in the detector of neutron emitted by the sample is measured, and this position is retraced back through intervening material(s) between the detector and the sample to determine the spacial geometry of the sample.

Abstract: A system for detecting and classifying small amounts of explosives and other controlled substances while rejecting confounders, including a source/detector array formed of a plurality of sources and a plurality of detectors, a signal processor coupled to the source/detector array for processing data received from the detectors, a classifier coupled to the signal processor for classifying data received from the signal processor according to a plurality of algorithms, a maximal rejection classifier coupled to the classifier; and a declarative decision module coupled to the maximal rejection classifier for rendering an accurate decision regarding the contents of the object is provided. The apparatus includes an enclosure, a shield layer disposed within the enclosure, a cavity disposed within the shield layer, a plurality of neutron sources and a detection array disposed within the cavity, and a transport mechanism for moving objects through the cavity past the sources and detection array.

Abstract: A first pulsed beam of charged particles from a particle accelerator is accelerated toward a first target that is configured to emit a fast neutron beam in response to being struck by an accelerated particle such that the fast neutron beam is directed toward a physical region. The last neutron beam includes a neutron having an energy sufficient to cause fission in a fissionable material. Data from a sensor configured to detect radiation of a fission product is accessed, and before accelerating a second pulsed beam of charged particles, whether the physical region includes a fissionable material based on the data from the sensor is determined.

Abstract: The present invention provides a nuclear activation apparatus for one or more fluid samples comprising the following modules; a means for introducing one or more fluid samples to a sample conduit, an activation thimble, comprising a section of sample conduit configured for multiple passes adjacent a radiation source, an absorber located adjacent to the activation thimble, and a detector located adjacent the sample conduit, wherein the relative arrangement of the modules can be altered specific to an application and the rate of flow of the fluid sample adjacent the radiation source can be controlled.

Abstract: Disclosed herein is a prompt gamma-ray detection apparatus for analyzing chemical materials using femtosecond pulse laser-induced neutrons, which can be effectively used in the nondestructive inspection of various materials, such as metals, coal, cement, radioactive materials and the like as well as explosives and chemical materials, and which can provide better measurement results for the analysis of basic materials, and a method of measuring prompt gamma-rays using the apparatus. The prompt gamma-ray detection apparatus is advantageous because it can non-destructively analyze the elements in a chemical sample using a femtosecond pulse laser-induced neutron generator that solves the problems of an atomic reactor for research or a radioactive isotope as a neutron radiation source.

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 method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Abstract: A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source.

Abstract: Apparatuses for detecting neutrons, and methods for fabricating such apparatuses, are provided. The neutron detection apparatus includes a cell configured to hold water. Further, the neutron detection apparatus provides a source of one or more high barns isotopes positioned in the cell and configured to absorb neutrons. Neutron absorption by the high barns isotope in the presence of water causes the formation of H2O2. Further, the presence of H2O2 in the cell indicates exposure of the cell to neutrons.

Abstract: Non-destructive testing method may include providing a source material that emits positrons in response to bombardment of the source material with photons. The source material is exposed to photons. The source material is positioned adjacent the specimen, the specimen being exposed to at least some of the positrons emitted by the source material. Annihilation gamma rays emitted by the specimen are detected.

Abstract: A method and device for explosives identification bombards a sample with neutrons the energy of which is to the positron activation energy of nitrogen and to the required energy for a neutron proton nuclear reaction of neutrons with 16O to 16N. Electron positron annihilation radiation emitted by the sample due to the neutron bombardment is then detected as a function of time. The respective concentration and the concentration ratio of oxygen and nitrogen in the sample is determined from the time dependency of the annihilation radiation, and the explosive is identified by the comparison of the concentration ratios of the specific concentrations of oxygen and nitrogen with the corresponding substance ratios of known explosives. By radiation with neutrons at the same time radionuclides 13N are created from the nitrogen contained and 16N from the oxygen contained, the decay of which generates electron positron annihilation radiation with characteristic half-lives.

Abstract: A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

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 method for identifying at least one nuclear threat to homeland security, wherein such each nuclear threat is either hidden inside at least one cargo container before transit, or is placed inside at least one cargo container while in transit. Each such nuclear threat while interacting with its surroundings generates a unique nuclear threat signature.

Abstract: Various geometric constructs are configured for use in modeling a system, for example a fissile system, using an analysis method, such as Monte Carlo, to model such systems based upon the interstitial regions formed by these geometric constructs. The various geometric constructs are configured to provide for modeling of, for example, complex arrays and lattices and allows for embedding of these constructs and virtual filling of arrays of these modeled units.

Abstract: A cylindrical neutron generator is formed with a coaxial RF-driven plasma ion source and target. A deuterium (or deuterium and tritium) plasma is produced by RF excitation in a cylindrical plasma ion generator using an RF antenna. A cylindrical neutron generating target is coaxial with the ion generator, separated by plasma and extraction electrodes which contain many slots. The plasma generator emanates ions radially over 360° and the cylindrical target is thus irradiated by ions over its entire circumference. The plasma generator and target may be as long as desired. The plasma generator may be in the center and the neutron target on the outside, or the plasma generator may be on the outside and the target on the inside. In a nested configuration, several concentric targets and plasma generating regions are nested to increase the neutron flux.

Abstract: A method for evaluating a material specimen comprises: Mounting a neutron source and a detector adjacent the material specimen; bombarding the material specimen with neutrons from the neutron source to create prompt gamma rays within the material specimen, some of the prompt gamma rays being emitted from the material specimen, some of the prompt gamma rays resulting in the formation of positrons within the material specimen by pair production; collecting positron annihilation data by detecting with the detector at least one emitted annihilation gamma ray resulting from the annihilation of a positron; storing the positron annihilation data on a data storage system for later retrieval and processing; and continuing to collect and store positron annihilation data, the continued collected and stored positron annihilation data being indicative of an accumulation of lattice damage over time.

Abstract: A cargo inspection system and active inspection methods for operating the same to confirm or clear a presence of explosives and/or nuclear materials in cargo. The active inspection methods use high-energy photons and/or neutrons to induce fission, and measure prompt neutrons, delayed neutrons, and delayed gamma-rays. Additionally, if one or more suspect objects are identified within the cargo with a preceding radiographic or computed tomography scan, a microprocessor calculates a position that produces optimal active inspection signals. The cargo or one of a primary radiation source, a secondary radiation source, or one or more radiation detectors are moved to this calculated position before fission occurs.

Abstract: A remote sensing device for detecting materials of varying atomic numbers and systems and methods relating thereto. A system for identifying a material includes a photon beam flux monitor for resolving a high-energy beam. A method for identifying a material includes casting an incident photon beam on the material and detecting an emerging photon beam with an array of fission-fragment detectors, a first set of scintillator paddles, and a second set of scintillator paddles.

Abstract: The patent specification and claims disclose a neutron flux source supplying both monoenergentic neutrons and a spectrum of neutron energies similar to the neutron emission of 252Cf. The neutron flux source is applied to interrogate unknown materials in closed containers for classification of the contents.

Abstract: An analyser system (20) including an on-belt analyser having a housing (2) adapted to be positioned across a path of a conveyor belt (3) which carries material to be analysed, wherein the housing defines a tunnel (9) dimensioned to allow the belt to travel therethrough in suspended relation in order to allow analysis of the material without the belt contacting the analyser (1).

Abstract: A system for detecting and classifying small amounts of explosives and other controlled substances while rejecting confounders, including a source/detector array formed of a plurality of sources and a plurality of detectors, a signal processor coupled to the source/detector array for processing data received from the detectors, a classifier coupled to the signal processor for classifying data received from the signal processor according to a plurality of algorithms, a maximal rejection classifier coupled to the classifier; and a declarative decision module coupled to the maximal rejection classifier for rendering an accurate decision regarding the contents of the object is provided. The apparatus includes an enclosure, a shield layer disposed within the enclosure, a cavity disposed within the shield layer, a plurality of neutron sources and a detection array disposed within the cavity, and a transport mechanism for moving objects through the cavity past the sources and detection array.