Abstract: The active neutron spectrometer (1) comprises a polyhedral moderator body (2) of hydrogenated material having a first, a second and a third orthogonal main axis (X1, X2; Y1, Y2; Z1, Z2), a first series of thermal neutron detectors (3a1, 3a2, 3a3, 3a4, 3a5, 3a6, 3b1, 3b2, 3b3, 3b4, 3b5, 3b6) arranged along the first main axis (X1, X2), a second series of thermal neutron detectors (4a1, 4a2, 4a3, 4a4, 4a5, 4a6, 4b1, 4b2, 4b3, 4b4, 4b5, 4b6) arranged along the second main axis (Y1, Y2), and a third series of thermal neutron detectors (5a1, 5a2, 5a3, 5a4, 5a5, 5a6, 5b1, 5b2, 5b3, 5b4, 5b5, 5b6) arranged along the third main axis (Z1, Z2).

Abstract: The present invention relates to a metamaterial focal plane array for broad spectrum imaging. Electromagnetic energy in the form of light is absorbed in or on a metamaterial absorber and a subsequent hot carriers are collected either in a semiconductor space charge region (e.g. P-N junction), or in some other modern collection scheme. Following the accumulation of photogenerated charge (electrons or holes), the signal is then converted to a digital signal using conventional or slightly modified ROIC modules.

Abstract: A control apparatus may include a processor for calculating a detection efficiency, which is detected by a gamma-ray detection unit, of gamma-rays emitted from a sample stuffed into a first container. A shape of the first container is a shape which surrounds at least a part of the gamma-ray detection unit that detects the gamma-rays. An area inside the first container is divided into a plurality of similar areas which is area similar in shape to each other. The gamma-ray detection unit detects the gamma-rays emitted from the sample included in each the similar areas for each of the plurality of similar areas. The processor calculates the detection efficiency as a similar-area-detection efficiency based on a result of detection performed by the gamma-ray detection unit.

Abstract: A material detector includes a pulse generator to generate pulses to excite molecules in the material and a detector to detect a signal generated from excited molecules in the terahertz region. Spectral features in the material are analyzed to identify the material. Detection can be performed using a nanoantenna array structure having antennas tuned to detect the expected spectral emission. The nanoantenna array can include antennas having MIM or MIIM diodes. Signal processing and statistical analysis is use to reduce false positives and false negative in identifying the material.

Abstract: A water pumping and injecting multi-layered concentric sphere neutron spectrometer includes a neutron detector, a plurality of shells concentrically provided, and a water pumping and injecting device; wherein an innermost shell surrounds a surface of the neutron detector; gaps are formed between adjacent shells for containing liquid; the shells are made of an aluminum material; a valve is arranged on each of the shells except the innermost shell; the water pumping and injecting device is connected to the valve of each of the shells except the innermost shell, so as to input water into the gaps or output the water from the gaps. Compared with conventional neutron spectrometer, weight of the water pumping and injecting multi-layered concentric sphere device and the neutron spectrum detection system of the present invention is greatly reduced, which is conducive to transportation and utilization. Meanwhile, combination of neutron spectrum data measurement and measurement data are increased.

Abstract: In a high-resolution spectrally selective scanning microscopy of a sample, the sample is excited with illumination radiation in order to emit fluorescence radiation such that the illumination radiation is bundled into an illumination spot in or on the sample. The illumination spot is diffraction-limited in at least one spatial direction and has a minimum extension in said spatial direction. Fluorescence radiation emitted from the illumination spot is imaged into a diffraction image lying on an image plane in a diffraction-limited manner and is detected with a spatial resolution which resolves a structure of a diffraction image of the fluorescence radiation emitted from the illumination spot. The illumination spot is moved into different scanning positions. An individual image is generated for each scanning position, in a diffraction-limited manner onto a detector.

Abstract: A position determination system and a method for position detection within a wellbore are disclosed. A radioactive tag may be disposed within the wellbore. One or more scintillating optical fibers may be longitudinally disposed along a drill string, wireline, or the like, and run into the wellbore. A detector system is coupled to the optical fiber(s). A scintillating optical fiber emits short, bright flashes of visible light whenever exposed to the gamma radiation. When a scintillating flash is measured, it may be determined that the optical fiber is located within proximity to the radioactive tag. The amplitude of received pulses may be used to estimate where in the optical fiber scintillating events are occurring. By providing a second optical fiber coupled to a scintillating optical fiber, a time delay between received pulses may be used to indicate where along the scintillating optical fiber scintillation events are occurring.

Abstract: A multicolor fluorescence analysis device 11 is for detecting fluorescence emitted, as a result of excitation light irradiation, from a plurality of types of fluorophores included in a sample s, and is provided with an irradiation optical unit 520 for irradiating light emitted from a light source 510 onto a sample s as excitation light, a fluorescence condensation unit 530 having a fluorescence filter 531 that transmits light emitted from the sample s and transmits light of transmission wavelength bands different from the excitation wavelength bands, and a two-dimensional detector 554 that has a plurality of types of transmission filters 556 for transmitting prescribed wavelengths of light and detects the intensity of the light of the prescribed wavelength for each transmission filter 556, and the light emitted from at least two fluorophores from among the plurality of types of fluorophores is detected simultaneously and the fluorophore types are identified accordingly.

Abstract: A method of calibration-free scanned-wavelength modulation spectroscopy (WMS) absorption sensing is provided by obtaining absorption lineshape measurements of a gas sample on a sensor using 1f-normalized WMS-2f where an injection current to an injection current-tunable diode laser (TDL) is modulated at a frequency f, where a wavelength modulation and an intensity modulation of the TDL are simultaneously generated, extracting using a numerical lock-in program and a low-pass filter appropriate band-width WMS-nf (n=1, 2, . . .

Abstract: Disclosed is a portable non-destructive testing (NDT) instrument system that transmits spectrum data measured from a test material sample to a remotely located computer for computation of the sample's atomic element composition. The atomic element composition is subsequently transmitted back to the portable instrument for display to the operator in real time. The precision and accuracy of the compositional computation is improved by the greater processing power of the high performance remote computer. The operator of the NDT instrument may choose to use the remote computer to perform part or all of the compositional computation.

Abstract: To provide a charged particle beam analyzer enabling an efficient and high-sensitivity analysis of a microscopic light element contained in a heavy metal sample, the charged particle beam analyzer equipped with a WDX spectrometer includes a storage unit 126 having stored therein a correlation database between average atomic numbers and WDX background intensity values obtained with use of a plurality of standard samples and a WDX background processing means 146 including a means 147 for calculating an average atomic number for a sample 129 and a means for eliminating a WDX background intensity value derived from the average atomic number for the sample 129 and the correlation database from a WDX spectrum for the sample 129.

Abstract: Systems, methods, and devices for matching the lithology effect of a downhole tool having a lower-energy neutron source, such as AmBe, using a downhole tool having a higher-energy neutron source, such as an electronic neutron generator, are provided. One such downhole tool may include a neutron source, first and second neutron detectors, and data processing circuitry. The neutron source may emit neutrons into a subterranean formation, which may scatter off the formation. The first neutron detector may detect neutrons of a relatively lower spectrum of energies than the second neutron detector. From counts of these neutrons, the data processing circuitry may determine a property of the subterranean formation having a lithology effect that substantially matches another lithology effect associated with another downhole tool having a lower-energy neutron source.

Abstract: Systems and methods for neutron porosity well logging with high precision and reduced lithology effects are provided. In accordance with an embodiment, a downhole neutron porosity tool may include a neutron source, a neutron monitor, a neutron detector, and data processing circuitry. The neutron source may emit neutrons into a subterranean formation while the neutron monitor detects a count of neutrons proportional to the neutrons emitted. The neutron detector may detect a count of neutrons that scatters off the subterranean formation. The data processing circuitry may determine an environmentally corrected porosity of the subterranean formation based at least in part on the count rate of neutrons scattered off the subterranean formation normalized to the count rate of neutrons proportional to the neutrons emitted by the neutron source.

Abstract: A method and system for determining timing recovery information in a positron emission tomography (PET) system. One method includes determining energy information from pairs of light sensors of detectors of the TOF PET system, determining timing information from the pairs of light sensors of the detectors of the TOF PET system and calculating timing recovery information using the determined energy and timing information.

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 method and system for acquiring spectral information from an energy sensitive nuclear detector is disclosed. The method includes detecting nuclear radiation at a detection device and generating an electronic input pulse indicative of energy deposited in the detection device. The method further includes integrating the electronic input pulse at an integrating device to produce an integrated output signal and digitally sampling the integrated output signal of the integrating device at intervals to produce a stream of digital samples. The method further includes resetting the integrator synchronously with a sampling clock when a limit condition is reached.

Abstract: A neutron detector includes a coincidence detector to detect coincidence events in which each coincidence event indicates proximity in time of a first signal and a second signal. The first signal indicates detection of at least one of a neutron or a gamma ray, and the second signal indicates detection of a gamma ray by a gamma ray detector. A data processor identifies detection of neutron radiation based on characteristics of an energy spectrum of the gamma rays associated with the second signals that correspond to the coincidence signals.

Abstract: A terahertz spectrometer having a wider range of terahertz radiation source, high temporal resolution of scanning (<0.0.099 ?m or ˜0.3 pico second) over a wider range of scanning (up to ˜100 pico seconds). Also disclosed are exemplary applications of the spectrometer in biomedical, biological, pharmaceutical, and security areas.

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

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

Abstract: A Method for determining the material composition of a material sample which emits radiation comprises the following method steps: recording a spectrum of the energy deposited in a detector material by the radiation; determining a first energy deposited in a first energy range, a second energy deposited in a second energy range, and a third energy deposited in a third energy range; assigning a first colour parameter to the first deposited energy, a second colour parameter to the second deposited energy, and a third colour parameter to the third deposited energy; and comparing the assigned colour parameters with predetermined values for the colour parameters, the predetermined values typically corresponding to colour parameters of a predetermined material composition.

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

Abstract: According to an embodiment, a radioactivity evaluation method has: a first input step; a selection step in which the calculating section selects a representative neutron energy spectrum and a representative neutron fluence rate; a second input step; an radioactivity calculating step in which the calculating section calculates quantities of the radioactivity that correspond to the representative neutron energy spectra and the representative neutron fluence rates; a data storing step; a nuclide-by-nuclide radioactivation reaction rate calculating step in which the calculating section calculates a radioactivation reaction rate of each nuclide based on the neutron energy spectra at the position of each of the object sections; an object-by-object adding-up step; a nuclide determining step; and an object position determining step.

Abstract: The present invention aims at providing a method and apparatus for presenting, based on an enormous amount of data collected by an imaging mass analysis, information which is significant for understanding the tissue structure and other information of a biological sample and which is intuitively easy to understand to analysis operator. For each pixel 8b on a sample 8, the mass-to-charge ratio m/z (i) corresponding to the maximum intensity MI(i) in the mass spectrum is extracted, and all the pixels are grouped into clusters in accordance with their m/z (i). One cluster corresponds to one substance. Then, the largest maximum intensity MI(i) among the maximum intensities of the pixels included in a cluster is extracted as the representative maximum intensity MI(cj) for each cluster, and these representative maximum intensities MI(cj) are displayed with cluster number cj.

Abstract: A neutron detection system may include a volume of neutron moderating material, and a plurality of solid state neutron detection devices disposed within the volume of neutron moderating material, wherein some of the neutron detection devices suitable for transduction of primary reaction products resulting from a neutron interaction event, wherein some of the solid state neutron detection devices include two or more solid state neutron detection elements, and wherein the solid state neutron detection elements are configured for omnidirectional detection of impinging neutrons.

Abstract: A neutron detector system including a neutron sensitive reaction layer may be configured to react with incident neutrons to form energetic particles. An energetic particle capturing layer may be configured to capture energetic particles emitted from the neutron sensitive reaction layer and convert the kinetic energy of the captured energetic particles to heat. A microbolometer sensing element responsive to the heat may be configured to detect the incident neutrons.

Abstract: A method for detecting Special Nuclear Materials (SNM) or Radiological dispersion Devices (RDD), comprising: conveying an object along a predetermined path; imaging a distribution of radioactive sources associated with the object as it passes along said path; determining the presence and location of one or both of an RDD or SNM radioactive source within the object.

Abstract: A method is provided of calculating the structure of an inhomogeneous sample in which an electron beam is used to cause excitation of x-rays from the sample under known conditions of beam energy and geometry with respect to the sample. Notably the beam current is unknown. Measured x-ray intensity data for the sample corresponding to one or more sets of beam conditions and beam currents are firstly obtained, together with comparative x-ray intensity data for samples having known structures. A beam current factor for each beam condition is estimated and effective x-ray intensity data for each of the sets of conditions are then calculated using the measured and comparative x-ray intensity data and the beam current factor. The structure of the sample is then calculated for each of the sets of conditions using the effective x-ray intensity data. Predicting x-ray intensity data are produced corresponding to the calculated structure and compared with the effective x-ray intensity data.

Abstract: The invention provides a method of performing fast neutron detection or spectroscopy comprising selecting at least one isotope which exhibits fast neutron-induced charged particle reactions, selecting a host medium capable of performing radiation energy spectroscopy, combining the isotope and host medium into an interactive spectroscopic combination, exposing the combination structure to radiation comprising fast neutrons to provide a spectroscopic output, which includes at least one peak in the pulse-height spectrum whose height and amplitude correlate to the energy and intensity respectively of the incident neutrons; and processing the output to detect or to provide measurements of the energy and intensity of incident fast neutron radiation. The invention also provides a fast neutron spectrometer for use with the method.

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

Abstract: A method of improving energy determination of a Gamma event which interacts with a segmented scintillation detector, the method comprising: identifying radiation events detected by a detector that are likely not to have deposited their full energy in the detector, based only on characteristics of said detected events; and treating the identified radiation events differently from other radiation events that are likely to have deposited their full energy in the detector.

Abstract: A system and method for a heterogeneous capture-gated neutron detector are disclosed. The system includes an inorganic hydrogenous scintillating layer configured to emit at least one collision photon when contacted with a neutron having an energy greater than a predetermined value. A neutron capture layer is located adjacent the inorganic or organic hydrogenous scintillating layer and configured to capture the neutron and emit at least one gamma ray. The inorganic or organic hydrogenous scintillating layer is further configured to emit at least one capture photon in response to the at least one gamma ray from the neutron capture layer. Detection of the collision photon and capture photon designate a detected and captured neutron.

Abstract: Methods for monitoring target actinides in a fuel reprocessing or waste remediation facility. The methods can be characterized by providing a fuel reprocessing or waste remediation stream having at least one target actinide and at least one other radionuclide. At least a portion of the stream is flowed through an electrochemically modulated separations (EMS) device comprising a carbon-based electrode. A potential is applied to the carbon-based electrode to adjust the redox states of the target actinide, at least one of the radionuclides, or both. The target actinide is separated from the other radionuclides through reaction with, or at, the carbon-based electrode. Finally, direct, in-line chemical nondestructive analysis, at-line chemical separations and sampling analysis, or both, of the target actinide is performed.

Abstract: Mass analysis method and mass spectrometer in which the S/N of mass spectra does not deteriorate due to accumulation if an ionization method, such as MALDI, producing spectral intensities that are not uniform in time is employed. Every given number of collected mass spectra are accumulated and stored to produce primary accumulation mass spectra. After the measurements, some of the stored primary accumulation spectra are selected according to a given rule based on a time trace of the intensities of the primary accumulation mass spectra. The selected spectra are accumulated to produce a secondary accumulation mass spectrum.

Abstract: A neutron source detector is provided for detecting and determining an energy spectrum of a neutron source and a direction to the neutron source. The neutron source detector includes a detection system configured to detect and record the location and energy of interaction between a detector and a recoil proton produced by a scattering of a neutron emitted by the neutron source. A processor is configured to determine the energy of each of a plurality of recoil protons produced by respective scatterings of a neutron based on the recorded locations and energies of interactions of the recoil protons and determine and order scatter locations of the scattered neutron based on the determined energies of the recoil protons. A direction of the scattered neutron is determined based on the order of the scatter locations.

Abstract: A neutron detector has a volume of neutron moderating material and a plurality of individual neutron sensing elements dispersed at selected locations throughout the moderator, and particularly arranged so that some of the detecting elements are closer to the surface of the moderator assembly and others are more deeply embedded. The arrangement captures some thermalized neutrons that might otherwise be scattered away from a single, centrally located detector element. Different geometrical arrangements may be used while preserving its fundamental characteristics. Different types of neutron sensing elements may be used, which may operate on any of a number of physical principles to perform the function of sensing a neutron, either by a capture or a scattering reaction, and converting that reaction to a detectable signal. High detection efficiency, an ability to acquire spectral information, and directional sensitivity may be obtained.

Abstract: A Method for determining the material composition of a material sample which emits radiation comprises the following method steps: recording a spectrum of the energy deposited in a detector material by the radiation; determining a first energy deposited in a first energy range, a second energy deposited in a second energy range, and a third energy deposited in a third energy range; assigning a first colour parameter to the first deposited energy, a second colour parameter to the second deposited energy, and a third colour parameter to the third deposited energy; and comparing the assigned colour parameters with predetermined values for the colour parameters, the predetermined values typically corresponding to colour parameters of a predetermined material composition.

Abstract: A system and method for a heterogeneous capture-gated neutron detector are disclosed. The system includes an organic hydrogenous scintillating layer configured to emit at least one collision photon when contacted with a neutron having an energy greater than a predetermined value. A neutron capture layer is located adjacent the organic scintillating layer and configured to capture the neutron and emit at least one gamma ray. The organic scintillating layer is further configured to emit at least one capture photon in response to the at least one gamma ray from the neutron capture layer. Detection of the collision photon and capture photon designate a detected and captured neutron.

Abstract: A method of detecting explosives in a vehicle includes providing a first rack on one side of the vehicle, the rack including a neutron generator and a plurality of gamma ray detectors; providing a second rack on another side of the vehicle, the second rack including a neutron generator and a plurality of gamma ray detectors; providing a control system, remote from the first and second racks, coupled to the neutron generators and gamma ray detectors; using the control system, causing the neutron generators to generate neutrons; and performing gamma ray spectroscopy on spectra read by the gamma ray detectors to look for a signature indicative of presence of an explosive. Various apparatus and other methods are also provided.

Abstract: A fast and rigorous multivariate curve resolution (MCR) algorithm is applied to remotely sensed spectral data. The algorithm is applicable in the solar-reflective spectral region, comprising the visible to the shortwave infrared (ranging from approximately 0.4 to 2.5 ?m), midwave infrared, and thermal emission spectral region, comprising the thermal infrared (ranging from approximately 8 to 15 ?m). For example, employing minimal a priori knowledge, notably non-negativity constraints on the extracted endmember profiles and a constant abundance constraint for the atmospheric upwelling component, MCR can be used to successfully compensate thermal infrared hyperspectral images for atmospheric upwelling and, thereby, transmittance effects. Further, MCR can accurately estimate the relative spectral absorption coefficients and thermal contrast distribution of a gas plume component near the minimum detectable quantity.

Abstract: A portable hand-held system for identification of a radiation source includes a portable detection unit that detects gamma radiation, X-ray radiation and neutron radiation emitted due to nuclear decay in the radiation source being inspected and provides a corresponding detection signal based on the radiation. A radioisotope analysis unit analyzes radiation detected by the detection unit for determining radioisotope information. A display unit for displaying results of the analysis to a user, including radiation spectrum and the radioisotope information. A GPS receiver provides a current position information. A connecting unit communicates the results of the analysis and the current location to a remote computer. The detection unit, the radioisotope analysis unit, the display unit, the GPS receiver and the connecting unit form an integral device. The common housing includes a personal communicator with a microprocessor for the analyzing of the radiation spectra.

Abstract: A method of and a system for using electromagnetic frequency response to identify an unknown individual or authenticate the identity of an individual transmits an electromagnetic signal into a body part of the individual is positioned in a magnetic field. An electromagnetic signal is received from the body part and captured. The frequency spectrum of the captured electromagnetic signal is analyzed to identify, or authenticate the identity of, the individual. Identification is performed by comparing the captured frequency spectrum, or characteristics extracted from the captured frequency spectrum, of the unknown individual to those of known individuals. Authentication is performed by comparing the captured frequency spectrum, or characteristics extracted from the captured frequency spectrum, of an individual to the authentic frequency spectrum, or characteristics extracted from the authentic frequency spectrum, of the individual.

Abstract: A method and device for evaluating a printing medium for use in a printing process, in which a set of spectral data is generated from a sample of the printing medium, and the set of spectral data is analysed. The analysis of the set of spectral data comprises detecting spectral data of the set indicative of features of the printing medium related to performance of that printing medium in the printing process. The performance of the printing medium in the printing process is predicted in response to the detected spectral data of the set indicative of performance-related printing medium features, and the printing medium is accepted or refused for use in the printing process in response to this printing medium performance prediction.

Abstract: A process for measuring the moisture content in a quantity of PuO2 powder. The process detects the content of thermal neutrons emitted by the quantity of PuO2 powder and then deduces its moisture content from a value of the detected content assuming a relation determined between the proportion of thermal neutrons emitted by a quantity of PuO2 powder and the known moisture content in this quantity of PuO2 powder.

Abstract: A neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The flat embodiment of the neutron spectrometer is a chamber, a group of detectors each having an absorber layer, with each detector separated by gaps and arranged in an egg-crate-like structure within the chamber. Each absorber layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: A neutron spectrometer for aircraft is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The preferred dodecahedron embodiment of the neutron spectrometer is a solid, polyethylene dodecahedron assembly with 12 surface facets covered by a solid-state detector stacked on an absorbing layer composed of tantalum. Each absorbing layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: A solid-state image sensor, which has a two-dimensional matrix of a plurality of pixels used to sense the two-dimensional spatial distribution of radioactive rays, light rays, electrons, ions, or the like, is provided with an aperture that extends through a substrate at an image sensing unit on which the pixels are arranged, and a signal transfer path that connects signal transfer electrodes for reading images of the respective pixels kept clear of the aperture. Furthermore, the image sensing unit is divided into at least two regions by a boundary including the aperture, and these regions have individual signal read registers. With this structure, the image sensor serves as both an image sensor for sensing the two-dimensional distribution of radiation or the like, and an aperture for passing such radiation.

Abstract: A neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The flat embodiment of the neutron spectrometer is a chamber, a group of detectors each having an absorber layer, with each detector separated by gaps and arranged in an egg-crate-like structure within the chamber. Each absorber layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.

Abstract: Methods and apparatus involving neutron resonance radiography are used to map the elemental composition of an object. Sets of neutrons having energies within particular energy bands are directed through an object to be imaged. The attenuation of the neutrons passed through the object is detected, and that data can be used to detect explosives, weapons, drugs and other contraband.

Abstract: A neutron spectrometer is provided by a series of substrates covered by a solid-state detector stacked on an absorbing layer. As many as 12 substrates that convert neutrons to protons are covered by a layer of absorbing material, acting as a proton absorber, with the detector placed within the layer to count protons passing through the absorbing layer. By using 12 detectors the range of neutron energies are covered. The flat embodiment of the neutron spectrometer is a chamber, a group of detectors each having an absorber layer, with each detector separated by gaps and arranged in an egg-crate-like structure within the chamber. Each absorber layer is constructed with a different thickness according to the minimum and maximum energies of neutrons in the spectrum.