756results about "Neutron radiation measurement" patented technology

A system to detect an article includes one or more terahertz modules. Each module either generates or receives, or both generates and receives, terahertz radiation. Some of the terahertz radiation is reflected from the article and the remainder of the terahertz radiation is transmitted through the article. A processor analyzes the reflected and transmitted terahertz radiation to characterize the article.

A new and improved confocal fluorescence microscope is presented. The new microscope has significant advantages relative to existing implementations of microscope confocal imagers. In common with previous confocal imagers the instant invention has the advantages relative to conventional wide-field and confocal fluorescence imagers, however it addresses the drawbacks of confocal technology in terms of cost and complexity, and provides significant savings in both due to the simplicity of the components and the elimination of the need of, in particular, spatial filters such as pinholes or slits.

In one embodiment, a method of examining contents of an object is disclosed comprising scanning an object at first and second radiation energies, detecting radiation at the first and second energies, and calculating a function of the radiation detected at the first and second energies, for corresponding pixels. A pixel is a projection of radiation through the object onto the detector. The first functions of a plurality of pixels are grouped and a second function of the group is analyzed to determine whether the object at least potentially contains material having an atomic number greater than the predetermined atomic number. The second function may be compared to a third function, which may be a threshold having a value based, at least in part, on material having a predetermined atomic number. Systems are also disclosed.

A detector for detecting neutrons and gamma radiation includes a cathode that defines an interior surface and an interior volume. A conductive neutron-capturing layer is disposed on the interior surface of the cathode and a plastic housing surrounds the cathode. A plastic lid is attached to the housing and encloses the interior volume of the cathode forming an ionization chamber, into the center of which an anode extends from the plastic lid. A working gas is disposed within the ionization chamber and a high biasing voltage is connected to the cathode. Processing electronics are coupled to the anode and process current pulses which are converted into Gaussian pulses, which are either counted as neutrons or integrated as gammas, in response to whether pulse amplitude crosses a neutron threshold. The detector according to the invention may be readily fabricated into single or multilayer detector arrays.

The present invention provides a system, device, computer program product and article for a telepositional dosimeter (TPD) and a radiation measurement system (RMS) having one or more TPDs capable of communicating environmental radiation measurements to a network, database or other data management technology. The present invention combines radiation measurement technology, wireless network and mobile communication technology, software, and related technologies to enable applications in various environments including the areas of environmental protection, homeland security, anti-terrorism, nuclear safety, radiation material handling and safety, and emergency response.

The present invention provides a multi-view X-ray inspection system. In one embodiment, a beam steering mechanism directs the electron beam from an X-ray source to multiple production targets which generate X-rays for scanning which are subsequently detected by a plurality of detectors to produce multiple image slices (views). The system is adapted for use in CT systems. In one embodiment of a CT system, the X-ray source and detectors rotate around the object covering an angle sufficient for reconstructing a CT image and then reverse to rotate around the object in the opposite direction. The inspection system, in any configuration, can be deployed inside a vehicle for use as a mobile detection system.

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.

Described herein is system for the inspection of a target object. The system may include a gamma radiation source, a gamma detector and an image processor coupled to the gamma detector. When the inspection system is operating in a first active mode for imaging a target object, the gamma radiation source directs radiation at a target object, the radiation passes through the target object, and the image processor images the target object based on an output of the gamma detector. When the dual-mode system is operating in a second passive mode for imaging a target object, the target object is scanned by a neutron detector for radiation that is emitted by the target object, the emitted radiation from the target object is detected by the neutron detector and an indicator indicates the presence of the emitted radiation.

A neutron detector technology based on 10B thin film conversion of neutrons and detection of neutron capture reaction products in a counter gas within a thin straw tube detector body is described. This neutron detector is based on gas-filled thin wall straw tubes, modified for the conversion of neutrons in a very thin coating, or layer, of 10B, applied for example as a sputter-coated film of 10B4C, that lines the interior, or inside of the straw tube surface; and the subsequent detection of the neutron reaction products in the counter gas. One embodiment of this invention employs a closely-packed array of 10B4C-lined straw tubes employing a very thin and therefore high efficiency 10B4C layer, hence removing the barrier to efficient neutron capture reaction product escape while still providing for efficient neutron capture by providing a plurality of very thin 10B converters, each individual converter element providing efficient reaction product escape. Using such densely packed straw tube detectors of small diameter, a reasonable stack depth allows a high neutron detection efficiency to be achieved on the 1–10Å wavelength range of thermal neutrons. The position of each interacting neutron can be accurately obtained with for example, resistive charge division readout combined with straw decoding electronics to determine the identity of the struck straw.

A method for detecting an explosive in an object under investigation involves the initial X-ray irradiation of the object under investigation, e.g. a piece of luggage or mailing, and forming its X-ray images; using the X-ray images to detect areas with a high density of organic materials and identifying articles therein; determining the location, dimensions and supposed mass of an unidentified article; determining and forming a directional pattern of the neutron radiator corresponding to the dimensions of the unidentified article. The method further includes subsequent thermal neutron irradiation of the area with the unidentified article; recording gamma-ray quanta having the energy of 10.8 MeV and cascade gamma-ray quanta with energies of 5.534 and 5.266 MeV by at least two gamma-ray detectors; counting of simultaneously recorded pairs of cascade gamma-ray quanta; determination of the overall gamma-ray intensity, taking into account weight factors in readings of the detectors; determination of the threshold value for the overall gamma-ray intensity basing on the supposed mass of explosive being detected; and making a decision in the event the threshold value of overall gamma-ray intensity is exceeded. When checking small-size objects, the neutron irradiation step is preceded by replacing the ambient air by a gaseous medium not containing nitrogen.

A self-powered integral in-core instrument thimble assembly for monitoring the temperature and radiation levels surrounding a nuclear fuel assembly, that transmits output signals wirelessly to a remote location. The in-core instrument thimble assembly is activated by a short exposure within a reactor core and remains active after the fuel assembly is removed from the reactor core to continuously provide a remote monitoring capability for the fuel assembly as it is transported or stored at a remote location, without an external power source.

Certain aspects pertain to aperture-scanning Fourier ptychographic imaging devices comprising an aperture scanner that can generate an aperture at different locations at an intermediate plane of an optical arrangement, and a detector that can acquire lower resolution intensity images for different aperture locations, and wherein a higher resolution complex image may be constructed by iteratively updating regions in Fourier space with the acquired lower resolution images.

An in-core neutron monitor that employs vacuum microelectronic devices to configure an in-core instrument thimble assembly that monitors and wirelessly transmits a number of reactor parameters directly from the core of a nuclear reactor without the use of external cabling. The in-core instrument thimble assembly is substantially wholly contained within an instrument guide tube within a nuclear fuel assembly.

A portable survey instrument and methodology yield intensity of neutron radiation, intensity of gamma radiation, and a direction of impinging gamma radiation. The instrument uses a neutron detector surrounded by an essentially rectangular moderator with preferably four gamma ray detectors disposed symmetrically about the neutron detector and within the moderator. Material and dimensions of the moderator are selected so that the neutron-measurement is equally sensitive to fast and thermal neutrons. The moderator also induces angular responses to the gamma ray detectors. Responses of the gamma ray detectors are combined to yield a parameter indicative of the angular position of a source. The survey instrument is portable and suited for hand held use.

A portable survey instrument and methodology yield intensity of neutron radiation, intensity of gamma radiation, and a direction of impinging gamma radiation. The instrument uses a neutron detector surrounded by an essentially rectangular moderator with preferably four gamma ray detectors disposed symmetrically about the neutron detector and within the moderator. Material and dimensions of the moderator are selected so that the neutron measurement is equally sensitive to fast and thermal neutrons. The moderator also induces angular responses to the gamma ray detectors. Responses of the gamma ray detectors are combined to yield a parameter indicative of the angular position of a source. The survey instrument is portable and suited for hand held use.

Systems and methods for generating X-rays and neutrons using a single linear accelerator are disclosed. Such system and methods may interrogate an object at times with X-rays and at other times with neutrons, e.g., after suspicious material is detected based on the X-rays. A system may include a single linear accelerator for generating first and second electron beams; first and second targets; a magnet configured to control irradiation of the first and second targets by the first and second electron beams; and a controller that (a) causes the linear accelerator to generate the first electron beam and causes the magnet to direct the beam to first target to generate X-rays; and (b) causes the linear accelerator to generate the second electron beam and causes the magnet to direct the beam to the second target to generate neutrons.

A system and method for detecting radiation from a source in a container is disclosed. A continuous optical fiber path is disposed in a medium which is part of or associated with a container and which totally encapsulates the inside volumetric space of the container. The optical fiber path provides a volumetric mass of optical fiber which is reactive to radiation from a radiation source in the container to cause an irreversible change in the light carrying capacity or other characteristic of the optical fiber. A light source is coupled to one end of the optical fiber path for introducing light having a predetermined characteristic. A light detector is coupled to the other end of the optical path for receiving light from the optical path. A circuit is coupled to the light detector and is operative to detect a change in the predetermined characteristic of the light and to provide an indication thereof in a fail-safe manner. The extraction of a radiation signal from background radiation noise is achieved using geometric methodologies. The detection system is operative to facilitate the detection of low level flux of thermalized neutrons.

A computerized system 40 for locating a device. System 40 includes a sensor module 20 and a CPU 42. A radioactive source 38, associated with the device, produces a signal in the form of radioactive disintegrations. Module 20 includes a radiation detector 22 capable of receiving a signal from source 38 attached to the device. Module 20 produces an output signal 34. CPU 42 receives output signal(s) 34 and translates output 34 into directional information relating to a position of source 38.

The present invention provides a method and system for measuring the spatial distribution of fluorescence from the excited radiochromic luminescent material; and for signal processing of the spatial distribution of fluorescence to thereby detect tracks of one or more heavy charged particles with which the luminescent material has been irradiated. The present invention also provides a method and system for measuring the spatial distribution of fluorescence from an excited radiochromic luminescent material that has been irradiated with a hot particle of a radioactive material. The present invention provides a method for detecting thermal and fast neutrons as well as a method for determining parameters of heavy charge particles. In several embodiments of the present invention, the luminescent material comprises Al2O3 doped with magnesium and carbon.

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 μm), midwave infrared, and thermal emission spectral region, comprising the thermal infrared (ranging from approximately 8 to 15 μm). 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.

To improve the problems of conventional mine detectors, the purpose of the present invention is to provide a smart wearable mine detector comprising a human body antenna unit 100, a main microprocessor unit 200, a smart eyeglasses unit 300, a body-mounted LCD monitor unit 400, a wireless data transmission and reception unit 500, a belt-type power supply unit 600, a black box-type camera unit 700, and a security communication headset 800, the smart wearable mine detector: can be detachably worn on the head, torso, arm, waist, leg and the like of a body while a combat uniform is worn, thereby having excellent compatibility with conventional combat uniforms; enables a human body antenna unit which is detachably attached to a body and detects a mine through a super high-frequency RF beam and a neutron technique to be applied so as to detect the mine by identifying metals, nonmetals, and initial explosives of the mine; enables mines buried on the ground and under the ground to be detected in all directions (360°), and a distance, location, form, and materials of the mines to be exhibited on smart eyeglasses and a body-mounted LCD monitor unit in real time as 2D or 3D images such that a combatant can engage in battle avoiding mines, thereby improving combat efficiency by 90% when compared to existing combat efficiency; enables a battle to be carried out for three to seven days through a twin self-power supply system of a portable battery and a belt-type power supply unit even without need for charging power; and enables combat situations in a remote place to be monitored, in real time, in a remote combat command server, and allows each combatant to share combat information one to one such that it is possible to construct a smart combat command system capable of remotely commanding real combat situations as if one was on site of the battle.

The invention concerns radiographic equipment. The equipment includes a source of substantially mono-energetic fast neutrons produced via the deuterium-tritium or deuterium-deuterium fusion reactions, comprising a sealed-tube or similar generator for producing the neutrons. The equipment further includes a source of X-rays or gamma-rays of sufficient energy to substantially penetrate an object to be imaged and a collimating block surrounding the neutron and gamma-ray sources, apart from the provision of one or more slots emitting substantially fan-shaped radiation beams. Further included is a detector array comprising a multiplicity of individual scintillator pixels to receive radiation energy from the sources and convert the received energy into light pulses, the detector array aligned with the fan-shaped beams emitted from the source collimator and collimated to substantially prevent radiation other than that directly transmitted from the sources reaching the array. Conversion means are included for converting the light pulses produced in the scintillators into electrical signals. Conveying means are included for conveying an object between the sources and the detector array. Computing means are included for determining from the electrical signals the attenuation of the neutrons and the X-ray or gamma-ray beams and to generate output representing the mass distribution and composition of the object interposed between the source and detector array. The equipment further includes a display means for displaying images based on the mass distribution and the composition of the object being scanned.

A method of detecting and transmitting radiation detection information to a network. The method including: communicating with one or more personal radiation detection devices, each device including, a host memory, an event memory, a microprocessor, a global positioning unit and a transceiver or a transmitter; a radiation shield around the host memory and the event memory; a radiation detection memory, the radiation detection memory, responsive to alpha radiation and including two or more SRAM arrays including cross-coupled invertors coupled to wordlines through different value capacitors; a conversion device including a material able to convert neutron and / or gamma radiation into alpha radiation; and an event detection circuit configured to detect and to store data relative to detection of the alpha radiation events by the radiation detection memory; storing the data in the event memory; and retrieving, in a reading device of the network, the data stored in the event memory.

A tube-style neutron detector, a panel-style neutron detector incorporating a plurality of tube-style neutron detectors, and a panel-style neutron detector including a plurality of anode wires are provided. A plurality of channels is provided in a neutron detector such that each channel has an inner surface of a coating layer including a neutron-absorbing material. A wire anode is provided at end of each channel so that electrons generated by a charged daughter particle generated by a neutron are collected to detect a neutron-matter interaction. Moderator units can be incorporated into a neutron detector to provide improved detection efficiencies and / or to determine neutron energy spectrum. Gas-based proportional response from the neutron detectors can be employed for special nuclear material (SNM) detection. This neutron detector can provide similar performance to 3He-based detectors without requiring 3He and without containing toxic, flammable, or high-pressure materials.

At least one pair of hodoscope radiation monitors arranged to simultaneously monitor a target region that contains a source of radiation. The hodoscopes are preferably arranged so that their fields of view of the region are approximately orthogonal. The fields of view of the two detectors will overlap in a region that contains the source of radiation. Each of the two detectors will record radiation from the overlap region and, in addition, will record background radiation emanating from other regions within detector fields of view. The present invention provides statistical correlation techniques to estimate the extent to which unusually high radiation originates in the overlap region, irrespective of background in the field-of-view of individual hodoscope detectors. The source of radiation might be spontaneous, might be from an activation process, or might be scattered in from an external beam.

A vehicle-based threat detection system (10) for detecting weapons in a vehicle includes at least one sensor (12) in a cargo holding area of the vehicle. The sensor (12) is connected to at least one detector (14) that detects presence of a weapon in the cargo holding area. A warning system (16) is capable of communicating detection of a weapon to a location remote from the cargo holding area.

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.

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.