2593 results about "Gamma ray" patented technology

A single crystal having the general composition, Ce2x(Lu1-yYy)2(1-x)SiO5 where x=approximately 0.00001 to approximately 0.05 and y=approximately 0.0001 to approximately 0.9999; preferably where x ranges from approximately 0.0001 to approximately 0.001 and y ranges from approximately 0.3 to approximately 0.8. The crystal is useful as a scintillation detector responsive to gamma ray or similar high energy radiation. The crystal as scintillation detector has wide application for the use in the fields of physics, chemistry, medicine, geology and cosmology because of its enhanced scintillation response to gamma rays, x-rays, cosmic rays and similar high energy particle radiation.

The invention provides methods and apparatus for detecting radiation including x-ray photon (including gamma ray photon) and particle radiation for radiographic imaging (including conventional CT and radiation therapy portal and CT), nuclear medicine, material composition analysis, container inspection, mine detection, remediation, high energy physics, and astronomy. This invention provides novel face-on, edge-on, edge-on sub-aperture resolution (SAR), and face-on SAR scintillator detectors, designs and systems for enhanced slit and slot scan radiographic imaging suitable for medical, industrial, Homeland Security, and scientific applications. Some of these detector designs are readily extended for use as area detectors, including cross-coupled arrays, gas detectors, and Compton gamma cameras. Energy integration, photon counting, and limited energy resolution readout capabilities are described. Continuous slit and slot designs as well as sub-slit and sub-slot geometries are described, permitting the use of modular detectors.

The invention consists in structuring scintillation radiation detectors as Photonic Bandgap Crystals or 3D layers of thin filaments, thus enabling extremely high spatial resolutions and achieving virtual voxellation of the radiation detector without physical separating walls. The ability to precisely measure the recoil electron track in a Compton camera enables to assess the directions of the gamma rays hitting the detector and consequently dispensing with collimators that strongly reduce the intensity of radiation detected by gamma cameras. The invention enables great enhancements of the capabilities of gamma cameras, SPECT, PET, CT and DR machines as well as their use in Homeland Security applications. Methods of fabrication of such radiation detectors are decribed.

A method for simultaneous transmission x-ray computed tomography (CT) and single photon emission tomography (SPECT) comprises the steps of: injecting a subject with a tracer compound tagged with a gamma-ray emitting nuclide; directing an x-ray source toward the subject; rotating the x-ray source around the subject; emitting x-rays during the rotating step; rotating a cadmium zinc telluride (CZT) two-sided detector on an opposite side of the subject from the source; simultaneously detecting the position and energy of each pulsed x-ray and each emitted gamma-ray captured by the CZT detector; recording data for each position and each energy of each the captured x-ray and gamma-ray; and, creating CT and SPECT images from the recorded data. The transmitted energy levels of the x-rays lower are biased lower than energy levels of the gamma-rays. The x-ray source is operated in a continuous mode. The method can be implemented at ambient temperatures.

In some embodiments, an image-guided radiotherapy apparatus and method is provided in which a radiotherapy radiation source and a gamma ray photon imaging device are positioned with respect to a patient area so that a patient can be treated by a beam emitted from the radiotherapy apparatus and can have images taken by the gamma ray photon imaging device. Radiotherapy treatment and imaging can be performed substantially simultaneously and/or can be performed without moving the patient in some embodiments. The gamma ray photon imaging device can be coupled and movable with respect to any part of a building structure, can be located on a portable frame movable to and from the radiotherapy radiation source and patient, or can take other forms. In some embodiments, the gamma ray photon imaging device can be used for imaging in connection with other types of medical interventions.

An improved applanation lens and method for use in an interface between a patient's eye and a surgical laser system does not discolor or lose light transmittance when subjected to gamma radiation. The improved applanation lens has an applanation surface configured to contact the eye upon application of a pressure. The lens is formed of high purity silicon dioxide (SiO₂) with purity great enough to resist discoloration upon prolonged irradiation by high-energy radiation such as UV, x-rays, gamma rays or neutrons, and is preferably a fused silica.

The invention provides methods and apparatus for detecting radiation including x-ray, gamma ray, and particle radiation for nuclear medicine, radiopaphic imaging, material composition analysis, high energy physics, container inspection, mine detection and astronomy. The invention provides detection systems employing one or more detector modules (102) comprising edge-on scintillator detectors (101) with sub-aperture resolution (SAR) capability employed, e.g., in nuclear medicine, such as radiation therapy portal imaging, nuclear remediation, mine detection, container inspection, and high energy physics and astronomy. The invention also provides edge-on imaging probe detectors for use in nuclear medicine, such as radiation therapy portal imaging, or for use in nuclear remediation, mine detection, container inspection, and high energy physics and astronomy.

In the present invention there is a provided an array of radiation detectors comprising at least one detector capable of detecting both low and high energy gamma radiation and adapted to provide spectrometric identification of the gamma source; at least one detector capable of detecting and providing spectrometric identification of fast neutrons and low resolution gamma spectra; at least one detector adapted to detect thermal neutrons; and, at least one plastic scintillator to give enhanced gamma ray sensitivity.

The presence of radiation shielding material concealing illegitimate content in a container is detected by obtaining each of measured gamma-ray data and measured neutron data from the container, and comparing the measured gamma-ray and neutron data to expected gamma-ray and neutron data. An anomaly between the measured data and the expected data is an indicum of the presence of such material shielding such illegitimate content.

An apparatus for the detection of extravasation in an imaging procedure includes at least a first source of energy to supply imaging energy to tissue in the vicinity of a site and at least a first sensor to measure a signal resulting from the energy supplied to the tissue by the first imaging energy source. In preferred embodiment, the energy may be one of X-ray, gamma ray or ultrasound energy.

An apparatus for investigating underground formations surrounding a borehole, comprises a tool body; a common gamma ray source mounted in the tool body and which, when the apparatus is positioned in a borehole, provides axi-symmetric distribution of gamma rays so as to provide substantially complete circumferential irradiation of the formation surrounding the borehole; and a detector for detecting gamma rays returning from the formation, the detector being responsive to gamma rays from only part of the borehole circumference. A method for investigating underground formations surrounding a borehole with a tool comprising a tool body having a gamma ray source and a detector mounted thereon, comprises irradiating the complete circumference of the borehole wall using a common gamma ray source which provides axi-symmetric distribution of gamma rays; and detecting gamma rays returning from the formation from only part of the borehole circumference.

A method for producing ²²⁹Th includes the steps of providing ²²⁶Ra as a target material, and bombarding the target material with alpha particles, helium-3, or neutrons to form ²²⁹Th. When neutrons are used, the neutrons preferably include an epithermal neutron flux of at least 1×10¹³ n s⁻¹·cm⁻². ²²⁸Ra can also be bombarded with thermal and/or energetic neutrons to result in a neutron capture reaction to form ²²⁹Th. Using ²³⁰Th as a target material, ²²⁹Th can be formed using neutron, gamma ray, proton or deuteron bombardment.

A radiation source is disclosed comprising a source of charged particles that travel along a path. Target material lies along the path to generate radiation upon impact by the beam. A magnet is provided to deflect the beam prior to impacting the target. The magnet may generate a time-varying magnetic field or a constant magnetic field. A constant magnetic field may be varied spatially across the beam. The magnet may be an electromagnet or a permanent magnet. In one example, deflection of the beam results in impact of the beam on the target along a plurality of axes. In another example, portions of the beam are differentially deflected. The source may thereby irradiate an object to be scanned with more uniform radiation. The charged particles may be electrons or protons and the radiation may be X-ray or gamma ray radiation, or neutrons. Scanning systems incorporating such sources, methods of generating radiation and methods of examining objects are disclosed, as well.

A method of diagnostic imaging in a shortened acquisition time for obtaining a reconstructed diagnostic image of a portion of a body of a human patient who was administered with dosage of radiopharmaceutical substance radiating gamma rays, using SPECT. The method comprises acquiring photons emitted from said portion of the body, by means of a detector capable of converting the photons into electric signals, wherein the total time of photon acquiring is substantially shorter than the clinically acceptable acquisition time; processing said electric signals by a position logic circuitry and thereby deriving data indicative of positions on said photon detector crystal, where the photons have impinged the detector; and reconstructing an image of a spatial distribution of the pharmaceutical substance within the portion of the body by iteratively processing said data.

A high-speed, three-dimensional, gamma-ray imaging method and system as well as a detector and array of such detectors for use therein are provided which characterize radioactivity distributions in nuclear and radioactive waste and materials facilities by superimposing radiation images on a view of the environment using see-through display screens or shields to provide a stereoscopic view of the radiation. The method and system provide real-time visual feedback about the locations and relative strengths of radioactive sources. The method and system dynamically provide continuous updates to the displayed image illustrating changes, such as source movement. A pair of spaced gamma-ray cameras of a detector subsystem function like “gamma eyes”. A pair of CCD cameras may be coupled to the detector subsystem to obtain information about the physical architecture of the environment. A motion tracking subsystem is used to generate information on the user's position and head orientation to determine what a user “sees”. The invention exploits the human brain's ability to naturally reconstruct a 3D, stereoscopic image from 2D images generated by two “imagers” separated by a known angle(s) without the need for 3D mathematical image reconstruction. The method and system are not only tools for minimizing human exposure to radiation thus assisting in ALARA (As Low As Reasonably Achievable) planning, but also are helpful for identifying contamination in, for example, laboratory or industrial settings. Other optically-invisible radiation such as infrared radiation caused by smoldering fires may also be imaged. Detectors are manufactured or configured in curvilinear geometries (such as hemispheres, spheres, circles, arcs, or other arrangements) to enable sampling of the ionizing radiation field for determination of positional activity (absolute or relative amounts of ionizing radiation) or spectroscopy (energy distributions of photons). More than one detector system may be used to obtain three-dimensional information. The detector systems are specifically suitable for direct visualization of radiation fields.

A method and apparatus for detecting radiation including x-ray, gamma ray, and particle radiation for radiographic imaging, and nuclear medicine and x-ray mammography in particular, and material composition analysis are described. A detection system employs fixed or configurable arrays of one or more detector modules comprising detector arrays which may be electronically manipulated through a computer system. The detection system, by providing the ability for electronic manipulation, permits adaptive imaging. Detector array configurations include familiar geometries, including slit, slot, plane, open box, and ring configurations, and customized configurations, including wearable detector arrays, that are customized to the shape of the patient. Conventional, such as attenuating, rigid geometry, and unconventional collimators, such as x-ray optic, configurable, Compton scatter modules, can be selectively employed with detector modules and radiation sources. The components of the imaging chain can be calibrated or corrected using processes of the invention. X-ray mammography and scintimammography are enhanced by utilizing sectional compression and related imaging techniques.

An energy dispersive x-ray and gamma-ray photon counter is described. The counter uses a photon sensor which incorporates a unique photocathode called Advanced Semiconductor Emitter Technology for X-rays (ASET-X) as its critical element for converting the detected photons to electrons which are emitted into a vacuum. The electrons are multiplied by accelerations and collisions creating a signal larger than the sensor noise and thus allowing the photon to be energy resolved very accurately, to within ionization statistics. Because the signal is already above the sensor noise it does not have to be noise filtered therefore allowing high-speed counting. The photon sensor can also be used as a device to visualize and image gamma-ray and x-ray sources.

A broad spectrum neutron detector has a thermal neutron sensitive scintillator film interleaved with a hydrogenous thermalizing media. The neutron detector has negligible sensitivity to gamma rays and produces a strong and unambiguous signal for virtually all neutrons that interact with the hydrogenous volume. The interleaving of the layers of thermal neutron sensitive phosphors helps ensure that all parts of the thermalizing volume are highly sensitive.

Inventions relate to scintillation substances and they may be utilized in nuclear physics, medicine and oil industry for recording and measurements of X-ray, gamma-ray and alpha-ray, nondestructive testing of solid states structure, three-dimensional positron-emission tomography and X-ray computer tomography and fluorography. Substances based on silicate comprising lutetium and cerium characterised in that compositions of substances are represented by chemical formulae Ce_xLu_2+2y−xSi_1−yO_5+y, Ce_xLi_q+pLu_{2−p+2y−x−z}A_zSi_1−yO_5+y−p, Ce_xLi_q+pLu_{9.33−x−p−z}□_0.67A_zSi₆O_26−p, where A is at least one element selected from group consisting of Gd, Sc, Y, La, Eu, Tb, x is value between 1×10⁻⁴ f.units and 0.02 f.units., y is value between 0.024 f.units and 0.09 f.units, z is value does not exceeding 0.05 f.units, q is value does not exceeding 0.2 f.units, p is value does not exceeding 0.05 f.units. Achievable technical result is the scintillating substance having high density, high light yield, low afterglow, and low percentage loss during fabrication of scintillating elements.

A method and apparatus of obtaining and reconstructing an image of a portion of a body, administered by a radiopharmaceutical substance, by using Single-photon emission computerized tomography (SPECT) for determination of functional information thereon. The method comprises (a) acquiring gamma ray photons emitted from said portion by means of a detector capable of converting the photons into electric signals, the detector having at least one crystal and allowing said gamma rays having incident angles essentially exceeding 5 degrees and, preferably, exceeding 10 degrees to be detected; (b) processing said electric signals by a position logic circuitry and thereby transforming them into data indicative of positions on said photon detector crystal, where the photons have impinged the detector; and (c) reconstructing an image of a spatial distribution of the pharmaceutical substance within the portion of the body by processing said data and taking into consideration weight values which are functions of angles and, possibly, distances between different elements of the portion of the body and corresponding elements of this position's projection on the detector.