Abstract:
A bulk material analyzer (FIG. 2) is variably constructed from an assembly of components The analyzer (FIG. 2) is the type that is used to analyze bulk material (28) transported on a conveyor belt (29) through an activation region (30) between at least one radiation source (element 11) and at least one radiation detector (12) within the bulk material analyzer (FIG. 2) The assembly includes a radiation-source box (11) for disposition either above the activation region (30) or below the conveyor belt (29), a radiation-detector box (12) for disposition on the opposite side of the activation region (30) and the conveyor belt (29) from the radiation-source box (11); and a set of stackable structural beams (14, 15, 16, 17, 18, 19) predominantly containing radiation shielding material and configured for stacking about the activation region (30), the radiation-source box (11) and the radiation-detector box (12) to prevent unwanted radiation being generated and transported to the radiation-detector box (12).
Abstract:
A bulk material analyzer (FIG. 2) is variably constructed from an assembly of components The analyzer (FIG. 2) is the type that is used to analyze bulk material (28) transported on a conveyor belt (29) through an activation region (30) between least one radiation source (element 11) and at least one radiation detector (12) within the bulk material analyzer (FIG. 2) The assembly includes a radiation-source box (11) for disposition either above the activation region (30) or below the conveyor belt (29), a radiation-detector box (12) for disposition on the opposite side of the activation region (30) and the conveyor belt (29) from the radiation-source box (11); and a set of stackable structural beams (14, 15, 16, 17, 18, 19) predominantly containing radiation shielding material and configured for stacking about the activation region (30), the radiation-source box (11) and the radiation-detector box (12) to prevent unwanted radiation being generated and transported to the radiation-detector box (12).
Abstract:
Nuclear gauges, their components and method for assembly and adjustment of the same are provided. The nuclear gauges are used in measuring the density and/or moisture of construction-related materials. The nuclear gauge can include a gauge housing having a vertical cavity therethrough and at least one radiation detector located within the housing. The nuclear gauge can include a vertically moveable source rod and a radiation source operatively positioned within a distal end of the source rod.
Abstract:
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.
Abstract:
Apparatus and method for discriminating against neutrons coming from directions other than a preferred direction and discriminating against gamma rays. Two photomultiplier (PM) tubes 9,10 are parallel to each other and are attached to one end of a light pipe 12. A neutron scintillator 13 is attached to the other end of the light pipe. The scintillator 13 is comprised of optical fibers arranged contiguously along a first direction, which is perpendicular to a length dimension of the optical fibers, and which optical fibers alternate between optical fibers which emit photons only in the lower portion of the electromagnetic spectrum and optical fibers which emit photons only in the higher portion of the electromagnetic spectrum. Typically, the optical fibers are about 100-250 microns. Filters 7,8 are between the PM tubes and the light pipe. One filter 7 transmits only photons in the lower end of the electromagnetic spectrum and the other filter 8 transmits only photons in the higher portion of the electromagnetic spectrum. Neutrons proceeding from a source which is parallel to the first direction will tend to cause only one optical fiber to emit photons. If neutrons enter the scintillator perpendicular to such first direction, photons will most likely be emitted by more than one optical fiber. A signal processing unit 11 will register a detected neutron if a signal is received from only one PM tube and will register a background event if signals are received from both PM tubes. If a gamma ray enters the detector and is detected, the scattered Compton electron most likely will cross two or more optical fibers, causing signals in both PM tubes. A signal processing unit 11 will register the event as a background event.
Abstract:
A device for measuring moisture content of soil and snow water storage has a first detector of cosmic neutrons passed through the soil placed deep in the soil at a pre-set depth, a second cosmic-ray neutron detector placed above the soil at an altitude which is greater than maximum snow pack thickness or vegetation layer height and spaced from the first neutron detector at a distance which is not greater than the path length of thermal neutrons in the atomosphere, and a soil background gamma-quantum radiation detector placed on the soil surface and spaced from the first neutron detector at a distance which is not greater than the gamma-quantum path length in the soil. Outputs of the neutron detectors and gamma-quantum radiation detector, are coupled to a respective series circuit, including a unit for detecting pulses of a predetermined amplitude, a pulse counter to which is connected a timer, and a recorder.
Abstract:
The present invention provides a method and system which is useful on instruments requiring experimentally determined calibration curves by which calibration data can be transferred to a plurality of field gauges, thereby avoiding the necessity of individually calibrating each gauge each time calibration is necessary. The field gauges are initially cross related to a master gauge. At a later time when a new calibration is necessary, the master gauge is calibrated using carefully prepared samples of a test material. Using the experimentally derived calibration curves with the cross relation data provides calibration data for the field gauges.
Abstract:
A process measurement system for measuring levels, interfaces and other characteristics related to products positioned between a fast neutron source and a detector that directly measures the transmitted fast neutrons. The system far exceeds the limitations of neutron backscatter, thermal neutron transmission and gamma techniques while avoiding problems associated with them. As shown, a fast neutron source is placed on one side of a vessel that is being monitored, and a detector is placed on the opposite side. Fast neutrons have excellent penetration properties and thus measurements through thick walls and across substantial distances are possible. A direct measurement of the fast neutrons transmitted through the vessel and/or product is made. This arrangement provides an output that is a direct function of the transmitted fast neutrons between the source and detector, and is not dependent upon inferential measurement where errors are encountered.
Abstract:
The thermal neutron absorption cross-section of a sample is measured by placing the sample in a sample container which surrounds a cavity within which a neutron source is positioned. A detector is positioned along a line parallel to an axis passing through the cavity. The source and detector are immersed in a moderator within a tank.
Abstract:
The formation of a permanent image of a fast neutron beam on cellulose nitrate film. The cellulose nitrate film is positioned between a converter film made of a suitable hydrogen-containing material, such as polyethylene, and the assembly attached to a back plate of aluminum. The neutron exposure is made with the neutrons impinging on the uncovered polyethylene face. Elastic scattering of fast neutrons by the nuclei of the hydrogen atoms in the polyethylene film produces protons which travel into the cellulose nitrate, leaving sensitized spikes therein. The cellulose nitrate film is etched by suspending in a sodium hydroxide solution and the image on the dry film viewed by transmitted light with the light source off the viewing axis.