Patent classifications
G01T1/163
Energy calibration with Lu spectrum subtraction
The present application relates generally to positron emission tomography (PET). It finds particular application in conjunction with energy calibration of a digital PET (DPET) detector and will be described with particular reference thereto. In one aspect, a difference spectrum is produced by finding a difference between a background radiation spectrum with no radioactive source loaded and a calibration source radiation spectrum with a radioactive source loaded. The difference spectrum may then be used to identify an energy peak.
Energy calibration with Lu spectrum subtraction
The present application relates generally to positron emission tomography (PET). It finds particular application in conjunction with energy calibration of a digital PET (DPET) detector and will be described with particular reference thereto. In one aspect, a difference spectrum is produced by finding a difference between a background radiation spectrum with no radioactive source loaded and a calibration source radiation spectrum with a radioactive source loaded. The difference spectrum may then be used to identify an energy peak.
Apparatus for measuring an internal radioactive contamination in an individual
The device (10) comprises a first detector (16) for a measurement on a thyroid and a second detector (18) for a measurement on a thorax. It comprises a portable device (14) for supporting detectors, comprising: a transverse support crossmember (20), at least one support leg (22) carrying said support cross-member (20), and a support member (28), borne by the crossmember (20), including first (28A) and second (28B) portions movable relative to one another in a longitudinal direction (X), the first movable portion (28A) bearing the first detector (16), and the second movable portion (28B) bearing the second detector (18).
Apparatus for measuring an internal radioactive contamination in an individual
The device (10) comprises a first detector (16) for a measurement on a thyroid and a second detector (18) for a measurement on a thorax. It comprises a portable device (14) for supporting detectors, comprising: a transverse support crossmember (20), at least one support leg (22) carrying said support cross-member (20), and a support member (28), borne by the crossmember (20), including first (28A) and second (28B) portions movable relative to one another in a longitudinal direction (X), the first movable portion (28A) bearing the first detector (16), and the second movable portion (28B) bearing the second detector (18).
GAMMA-RAY ATTENUATOR AND GAMMA-RAY SHIELD FOR GAMMA-RAY SPECTROSCOPY
The present disclosure provides a gamma-ray attenuator and a gamma-ray shield for use in gamma-ray spectroscopy. The gamma-ray attenuator is a sleeve comprising a wall, a distal end, and a proximal end. The distal end of the sleeve is closed, and the proximal end of the sleeve forms an opening. A copper insert, a tin insert and a tungsten insert are installed in the sleeve such that the copper insert is adjacent to the distal end and the tungsten insert is closest to the proximal end. The sleeve is comprised of one or more materials that do not substantially attenuate gamma-rays. The open end of the sleeve fits over a tungsten safe that is operable to hold a radionuclide sample. When fitted together, a gamma-ray attenuator and a safe comprise a gamma-ray shield.
GAMMA-RAY ATTENUATOR AND GAMMA-RAY SHIELD FOR GAMMA-RAY SPECTROSCOPY
The present disclosure provides a gamma-ray attenuator and a gamma-ray shield for use in gamma-ray spectroscopy. The gamma-ray attenuator is a sleeve comprising a wall, a distal end, and a proximal end. The distal end of the sleeve is closed, and the proximal end of the sleeve forms an opening. A copper insert, a tin insert and a tungsten insert are installed in the sleeve such that the copper insert is adjacent to the distal end and the tungsten insert is closest to the proximal end. The sleeve is comprised of one or more materials that do not substantially attenuate gamma-rays. The open end of the sleeve fits over a tungsten safe that is operable to hold a radionuclide sample. When fitted together, a gamma-ray attenuator and a safe comprise a gamma-ray shield.
APPARATUS FOR MEASURING AN INTERNAL RADIOACTIVE CONTAMINATION IN AN INDIVIDUAL
The device (10) comprises a first detector (16) for a measurement on a thyroid and a second detector (18) for a measurement on a thorax. It comprises a portable device (14) for supporting detectors, comprising: a transverse support crossmember (20), at least one support leg (22) carrying said support cross-member (20), and a support member (28), borne by the crossmember (20), including first (28A) and second (28B) portions movable relative to one another in a longitudinal direction (X), the first movable portion (28A) bearing the first detector (16), and the second movable portion (28B) bearing the second detector (18).
APPARATUS FOR MEASURING AN INTERNAL RADIOACTIVE CONTAMINATION IN AN INDIVIDUAL
The device (10) comprises a first detector (16) for a measurement on a thyroid and a second detector (18) for a measurement on a thorax. It comprises a portable device (14) for supporting detectors, comprising: a transverse support crossmember (20), at least one support leg (22) carrying said support cross-member (20), and a support member (28), borne by the crossmember (20), including first (28A) and second (28B) portions movable relative to one another in a longitudinal direction (X), the first movable portion (28A) bearing the first detector (16), and the second movable portion (28B) bearing the second detector (18).
Quantitative radioactivity monitor for assays of wildlife
The present disclosure is directed to a detection assembly for detecting radiation emitted by radionuclides present within an animal. The detection assembly includes a housing having one or more walls defining a chamber. The detection assembly also includes a cover removably positioned over the top end of the housing, with the cover being configured for receipt of the animal. Furthermore, the detection assembly includes a radiation sensor positioned within the chamber. The radiation sensor is configured to detect the radiation emitted by the radionuclides present within the animal. Additionally, the detection assembly includes a shield positioned around a first portion of the radiation sensor, with the shield being configured to at least partially shield the radiation sensor from environmental radiation. A second portion of the radiation sensor is unshielded to permit the radiation sensor to receive radiation emitted by the radionuclides present within the animal.
Quantitative radioactivity monitor for assays of wildlife
The present disclosure is directed to a detection assembly for detecting radiation emitted by radionuclides present within an animal. The detection assembly includes a housing having one or more walls defining a chamber. The detection assembly also includes a cover removably positioned over the top end of the housing, with the cover being configured for receipt of the animal. Furthermore, the detection assembly includes a radiation sensor positioned within the chamber. The radiation sensor is configured to detect the radiation emitted by the radionuclides present within the animal. Additionally, the detection assembly includes a shield positioned around a first portion of the radiation sensor, with the shield being configured to at least partially shield the radiation sensor from environmental radiation. A second portion of the radiation sensor is unshielded to permit the radiation sensor to receive radiation emitted by the radionuclides present within the animal.