Abstract: A device for detecting neutron emission comprises a housing, a moderator structure, a neutron detection element, and a plurality of plate electrodes. The housing provides an enclosure and shielding from radiation other than neutron emission. The moderator structure is positioned within the housing and is formed from energy absorbing material. The moderator structure includes a first side wall and a second side wall spaced apart and oriented parallel to one another. The neutron detection element includes a neutron reactive material deposited on a planar substrate. The plate electrodes are formed from electrically conductive material and spaced apart from one another. Each adjacent pair of plate electrodes has a voltage therebetween, wherein one neutron detection element is positioned between adjacent pairs of plate electrodes and the combination of plate electrodes and neutron detection elements is positioned between the first side wall and the second side wall of the moderator structure.

Abstract: Provided are a neutron monitor device and a neutron measurement method which make it easier to measure the intensity of the neutrons having the energy region of 10 KeV to several hundreds KeV. A neutron monitor device includes a first detector which includes a hemispherical first body formed of PE and having a radius of 31 mm, a first specimen containing GaN disposed at the center of the first body, a Cd layer provided on an outer surface of the first body, and a B layer provided inside the first body, and a second detector which includes a hemispherical second body formed of PE and having a radius of 27 mm, a second specimen containing GaN disposed at the center of the second body, a B layer provided on the outer surface of the second body, and a Cd layer provided inside the second body.

Abstract: A method for obtaining information about an unknown neutron source or an unknown material interacting with a known neutron source comprises the steps of: (a) providing a radiation detector capable of delivering a neutron energy information allowing the production of response histogram(s) as a function of neutron energy, (b) measuring with said radiation detector neutrons being emitted from said unknown neutron source or from said unknown material, (c) deriving from said measured neutrons a neutron energy spectrum, especially in form of a histogram, (d) normalizing said energy spectrum or histogram relative to a parameter or set of parameters derived from the measurement of a different variable, (e) comparing said normalized energy spectrum or histogram with known energy spectra or histograms, and (f) drawing conclusions on the basis of said comparison about the nature of the unknown neutron source or unknown material.

Abstract: A neutron detector that utilizes cells in which a liquid scintillator is contained in elongated detector tubes, with photo-detectors disposed at each end of the tube to measure scintillation light generated by incident neutrons. The liquid scintillator is an interblended mixture including an ionic liquid blended with a scintillation enhancer and/or a moderator and/or a controlled optical attenuator. A longitudinal position of an incident neutron is determined by the magnitudes of the scintillation light portions arriving at each photo-detector, which are proportional to the distances between the neutron interaction point and the photo-detectors. The cells are arranged in a closely-spaced parallel planar array to facilitate determining incident neutron location in two dimensions. A detector system utilizes a first detector array to detect fast neutrons, a thermalizer (e.g., polyethylene) to convert fast incident neutrons to thermal neutrons, and a second detector array to detect the thermal neutrons.

Abstract: An instrument for detecting radiation is provided, which comprises an inner core housing a neutron detector, and an outer core comprising a neutron-moderating material, the instrument further including at least one elongate thermal neutron guide located within the outer core and having an inner end that terminates proximal to the neutron detector. In use, the elongate thermal neutron guide channels thermal neutrons towards the neutron detector. Also provided is a method for using said instrument.

Abstract: An instrument for detecting radiation is provided, which comprises an inner core housing a neutron detector, and another core comprising a neutron-moderating material, the instrument further including at least one elongate thermal neutron guide located within the outer core and having an inner end that terminates proximal to the neutron detector. In use, the elongate thermal neutron guide channels thermal neutrons towards the neutron detector. Also provided is a method for using said instrument.

Abstract: A surface contamination monitoring system/method configured to correct the detected the radioactive net count rate (NCR) value of a whole-body surface contamination monitoring device based on monitored subject height and thickness is disclosed. The system includes a height detection means for determining the height of a monitored subject and a thickness detection means for determining the thickness of at least a portion of the monitored subject. The net count rate (NCR) is corrected based on the determined height and thickness of the monitored subject as applied to site calibration factor data and self-shielding factor data to produce a corrected net count rate (CNR). If the corrected net count rate (CNR) registers above a preset alarm threshold, the monitored subject is considered contaminated and an appropriate alarm is registered.

Abstract: Controlling electromagnetic (‘EM’) radiation in a data center having a number EM sections, including: receiving, by an EM controller, a specification of preferred EM radiation characteristics for the data center; and setting, by the EM controller, a state of each EM section in accordance with the specification, where the state of each EM section may be one of: an absorption state in which the EM section absorbs EM radiation or a reflection state in which the EM section reflects EM radiation.

Abstract: The invention provides a method for optimizing the spectroscopy performance of a spectroscopy scintillator by surrounding the scintillator by a reflector material, performing a scan measuring resolution and light output at three or more axial locations on the crystal, where at least one location is close to the PMT or below the crystal (near the PMT) at least one location is at the end away from the PMT of the scintillator), and adjusting the surface finish of the crystal and/or the reflector to obtain equal light output and optimal resolution over the length and different azimuth of the crystal.

Abstract: A system and method for correcting, based on a monitored subject's height and thickness, the net count rate value of a whole-body surface contamination monitoring device. The device includes a height detection means for determining the height of a subject being monitored, and a thickness detection means for determining the thickness of at least a portion of the body of the subject being monitored. The net count rate is based on site calibration factor data and self-shielding factor data, wherein both types of factor data consider the determined height and thickness.

Abstract: A method for determining the spectral and spatial distribution of a braking photon flow along at least one direction in space (x, y, z), characterized in that the method comprises measuring the neutrons resulting from the impact of the braking photons (ph) on at least one conversion target which is moved in the direction (x, y, z) in space. The invention can be used for X-rays, medical imaging, tomography, etc.

Abstract: The present invention includes an apparatus and method for neutron radiation detection. The apparatus comprises combining thin walled, boron-coated straw tubes with a plastic moderator material interspersed around the tubes. The method involves using such an apparatus through application of voltage to a central wire running inside the tubes and collecting electrical pulses generated thereby.

Abstract: A method for detecting neutron radiation in accordance with particular embodiments includes exposing a neutron detector array comprising at least one two-dimensional array of neutron detectors to a first scene of interest. The neutron detector array is based on at least one two-dimensional array of microbolometer detectors. The method also includes receiving a plurality of response values from a corresponding plurality of neutron detectors of the neutron detector array. The method further includes generating a comparison value based on the plurality of response values and a baseline response value. The method additionally, includes determining whether more than a first threshold amount of neutron radiation is being generated by the first scene based on the comparison value.

Abstract: A system and method of adapting a radiation therapy treatment plan for a patient by varying the fraction size delivered to the patient on any individual day, based at least partially on the use of daily patient registration (i.e., taking images of the patient before each fraction is delivered to see the position and size of the tumor on that day). The fraction size can be dynamically altered based upon the biology of the tumor.

Abstract: A system for determining an amount of radiation includes a dosimeter configured to receive the amount of radiation, the dosimeter comprising a circuit having a resonant frequency, such that the resonant frequency of the circuit changes according to the amount of radiation received by the dosimeter, the dosimeter further configured to absorb RF energy at the resonant frequency of the circuit; a radio frequency (RF) transmitter configured to transmit the RF energy at the resonant frequency to the dosimeter; and a receiver configured to determine the resonant frequency of the dosimeter based on the absorbed RF energy, wherein the amount of radiation is determined based on the resonant frequency.

Abstract: A system includes emission of a first treatment beam associated with a first energy toward a neutron dose detector, determination of a first number of soft errors experienced by a semiconductor-based device exposed to neutrons generated by the first treatment beam, determination of a first neutron dose based on the first treatment beam using the neutron dose detector, and association of the first energy of the first treatment beam with the first number of soft errors and the first neutron dose. Some aspects include emission of a second treatment beam associated with the first energy toward a target, determination of a second number of soft errors experienced by the semiconductor-based device exposed to neutrons generated by the second treatment beam, and determination of a second neutron dose at the target based on the association between the first energy, the first number of soft errors and the first neutron dose.

Abstract: Described is device comprising dosimeter for measuring one or more doses of radiation; and an RFID tag comprising an antenna for communicating with an RFID tag reader and non-volatile memory for storing data therein.

Abstract: The invention relates to a neutron dosimeter comprising a neutron moderator (12), a first radiation detector (14), which is situated in the neutron moderator (12) and is surrounded by a first metal body (28) containing material that can be activated by neutrons, a second radiation detector (16), which is situated in the neutron moderator (12) close to the first radiation detector (14) and is surrounded by a second metal body (30) that substantially cannot be activated by neutrons. The first metal body (28) and the second metal body (30) are designed in such a way that they substantially have the same degree of absorption of photons. The dosimeter also comprises an evaluation circuit, which is connected to the radiation detectors and is equipped to suppress electrical impulses generated by ionising radiation using a pulse intensity that lies below a predefined pulse intensity threshold.

Abstract: Described is device comprising dosimeter for measuring one or more doses of radiation; and an RFID tag comprising an antenna for communicating with an RFID tag reader and non-volatile memory for storing data therein.

Abstract: Disclosed is a nuclear radiation-warning detector that measures impedance of silver-silver halide on an interdigitated electrode to detect light or radiation comprised of alpha particles, beta particles, gamma rays, X rays, and/or neutrons. The detector is comprised of an interdigitated electrode covered by a layer of silver halide. After exposure to alpha particles, beta particles, X rays, gamma rays, neutron radiation, or light, the silver halide is reduced to silver in the presence of a reducing solution. The change from the high electrical resistance (impedance) of silver halide to the low resistance of silver provides the radiation warning that detected radiation levels exceed a predetermined radiation dose threshold.

Abstract: A system for determining an amount of radiation includes a dosimeter configured to receive the amount of radiation, the dosimeter comprising a circuit having a resonant frequency, such that the resonant frequency of the circuit changes according to the amount of radiation received by the dosimeter, the dosimeter further configured to absorb RF energy at the resonant frequency of the circuit; a radio frequency (RF) transmitter configured to transmit the RF energy at the resonant frequency to the dosimeter; and a receiver configured to determine the resonant frequency of the dosimeter based on the absorbed RF energy, wherein the amount of radiation is determined based on the resonant frequency.

Abstract: In a neutron dosimeter, G(L) function data, which causes the tendency of a characteristic when neutron energy is plotted along the horizontal axis and the ambient dose equivalent (1 cm dose equivalent) is plotted along the vertical axis to approximate a neutron fluence-ambient dose equivalent (1 cm dose equivalent) conversion coefficient curve (neutron energy-ICRP 74 H* (10) response curve), is used to compensate the output of a mixed gas detector which encapsulates a gas mixture of a nitrogen gas and an organic compound gas and outputs detection pulse signals with peaks according to the energies of detected neutrons.

Abstract: A system includes emission of a first treatment beam associated with a first energy toward a neutron dose detector, determination of a first number of soft errors experienced by a semiconductor-based device exposed to neutrons generated by the first treatment beam, determination of a first neutron dose based on the first treatment beam using the neutron dose detector, and association of the first energy of the first treatment beam with the first number of soft errors and the first neutron dose. Some aspects include emission of a second treatment beam associated with the first energy toward a target, determination of a second number of soft errors experienced by the semiconductor-based device exposed to neutrons generated by the second treatment beam, and determination of a second neutron dose at the target based on the association between the first energy, the first number of soft errors and the first neutron dose.

Abstract: A device and method for on line dosimetry monitoring of a hadron beam generated from a source of radiation and delivered to a target, the device comprising a plurality of support plates arranged in parallel in a face-to-face relation, separated from each other by gas filled gaps and perpendicularly to the central axis of said hadron beam, and forming a plurality of ionization chambers, each support plate having on a first side one or more collecting electrodes and on a second side one or more high voltage electrode, arranged in such a way that each support plate has said first side substantially opposed to said second side of another support plate. Each support plate has an opening so as to form an inner cavity for allowing the undisturbed passage of a central portion of the hadron beam delivered to said target and a peripheral region for intercepting and measuring, by means of said plurality of ionization chambers, a peripheral portion of said hadron beam.

Abstract: Disclosed is a dosimeter (1) for the detection of neutron radiation within an energy range of 0.025 eV to several hundred GeV, comprising a substantially spherical base body (3) which is used as a moderation body and which comprises hydrogenous material, a detection element (5) which is arranged in the center of the base body (3), and a neutron converter (7) surrounding the detection element (5). The neutron converter (7) comprises metal atoms which convert the energy of the high-energy neutron radiation essentially into neutrons within a suitable energy range. The dosimeter (1) is characterized in that the base body (3) is provided with an access (19) through which the detection element (5) can be introduced into the neutron converter (7) and removed thereform, and in that the neutron converter (7) is embodied in the form of a cylinder.

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

Abstract: Non-streaming high-efficiency perforated semiconductor neutron detectors, method of making same and measuring wands and detector modules utilizing same are disclosed. The detectors have improved mechanical structure, flattened angular detector responses, and reduced leakage current. A plurality of such detectors can be assembled into imaging arrays, and can be used for neutron radiography, remote neutron sensing, cold neutron imaging, SNM monitoring, and various other applications.

Abstract: The invention relates generally to a method for the calculation of radiation field distributions employing a new parallel 3-D radiation transport code and, a multi-processor computer architecture. The code solves algorithms using a domain decomposition approach. For example, angular and spatial domains can be partitioned into subsets and, the subsets can be independently allocated and processed.

Abstract: The invention relates generally to a method for the calculation of radiation field distributions employing a new parallel 3-D radiation transport code and, a multi-processor computer architecture. The code solves algorithms using a domain decomposition approach. For example, angular and spatial domains can be partitioned into subsets and, the subsets can be independently allocated and processed.

Abstract: Disclosed is a dosimeter (1) for the detection of neutron radiation within an energy range of 0.025 eV to several hundred GeV, comprising a substantially spherical base body (3) which is used as a moderation body and which comprises hydrogenous material, a detection element (5) which is arranged in the center of the base body (3), and a neutron converter (7) surrounding the detection element (5). The neutron converter (7) comprises metal atoms which convert the energy of the high-energy neutron radiation essentially into neutrons within a suitable energy range. The dosimeter (1) is characterized in that the base body (3) is provided with an access (19) through which the detection element (5) can be introduced into the neutron converter (7) and removed therefrom, and in that the neutron converter (7) is embodied in the form of a cylinder.

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

Abstract: 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.

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

Abstract: A method of measuring the activity of a radioisotope (3) placed in an ionisation chamber (1) consists in:—determining the energy spectrum of the radiation emitted by the radioisotope;—automatically comparing the energy spectrum with a set of pre-recorded or pre-programmed radioisotope energy spectra in such a way as to identify the radioisotope present;—subsequently, automatically directing the calibration coefficient corresponding to the radioisotope present to the electronic measuring elements in order to obtain the appropriate activity measurement. The invention provides a totally automatic activity measurement. Moreover, the invention also relates to an activity meter with radioisotope recognition which is used to obtain an automatic activity measurement. The device employs one or more scintillation—or semi-conductor-type radiation detectors (10) for determining the energy spectrum of the radioisotope present.

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

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

Abstract: A neutron rem meter utilizing proton recoil and thermal neutron scintillators to provide neutron detection and dose measurement. In using both fast scintillators and a thermal neutron scintillator the meter provides a wide range of sensitivity, uniform directional response, and uniform dose response. The scintillators output light to a photomultiplier tube that produces an electrical signal to an external neutron counter.

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