G01T1/362

Response function of a scintillator
11914087 · 2024-02-27 · ·

A method for generating a response function of a scintillator to incident gamma rays of energy within a range of energies of interest, the method including: obtaining the responses {S.sub.i} of the scintillator to a plurality of known radionuclides i (i=1, . . . N), each radionuclide i emitting gamma rays with known energetic properties (E.sub.ij, Y.sub.ij), decomposing, for each radionuclide i, response S.sub.i into primary responses of the scintillator S.sub.ij=(.sub.ij, Y.sub.ij, X.sub.ij), each primary response corresponding to the response of the scintillator to a received gamma ray of a known energy E.sub.ij for this radionuclide i, deriving from the primary responses {S.sub.ij} the response function (, X) of the scintillator to an incident gamma ray of any energy E within the range of energies of interest.

Indirect photon-counting analytical X-ray detector
10408949 · 2019-09-10 ·

An indirect, photon-counting X-ray detector capable of detecting the low-energy X-rays includes a scintillator screen that is directly coupled to a two-dimensional optical sensor. A signal filter receives an electrical output signal from the optical sensor and removes high intensity signal contributions therefrom that are indicative of direct interaction between said X-ray signal and said optical sensor. The scintillator screen has a sufficient thickness to ensure a high absorption of incident X-ray photons, and uses phosphor grains with a relatively small grain size. A cooling apparatus in thermal communication with the optical sensor may be used to control its temperature. The signal filter maintains a running average of changes in measured pixel output values for consecutive measurements, and replaces a measured value caused by a direct interaction event with a value equal to a previous measured value plus said running average.

Method and system for recovering scintillation pulse information

A method for recovering scintillation pulse information. The method comprises the steps: obtaining a scintillation pulse database of unstacked compliance single-events in a low count, and establishing a noise model of a scintillation pulse for the scintillation pulse database of the single-events; calculating a posterior probability logarithm value of a specific energy value according to the noise model of the scintillation pulse; and repeatedly calling the second step by means of calculations, and obtaining an energy value meeting a maximum posterior probability condition. A system for recovering scintillation pulse information. The system comprises a fluctuation model module, a posterior probability module, and an energy value search module. The method and system for recovering scintillation pulse information in the present invention effectively improve the precision of a system energy calculation, and is specifically suitable for an energy calculation of a sparse quantization level ADC digital nuclear instrument.

SYSTEM AND METHOD OF STABILIZATION OF A GAMMA AND NEUTRON DETECTING DEVICE

A spectroscopic gamma and neutron detecting device includes a scintillation detector that detects gamma and thermal neutron radiation, the scintillation detector including signal detection and amplification electronics, and a stabilization module configured to measure a pulse height spectrum of neutron radiation, determine a thermal neutron peak position in the neutron pulse height spectrum originating from cosmic ray background radiation, monitor the thermal neutron peak position in the neutron pulse height spectrum during operation of the spectroscopic gamma and neutron detecting device, and adjust the signal detection and amplification electronics based on the thermal neutron peak position in the neutron pulse height spectrum, thereby stabilizing the spectroscopic gamma and neutron detecting device.

Method for improving the energy resolution of gamma ray scintillation detectors; associated system, component and applications
10310103 · 2019-06-04 · ·

The invention concerns a method for improving the energy resolution of a gamma ray detector comprising a monolithic scintillator and a photodetector segmented during a scintillation event characterized by the following steps:detecting the time of arrival of the first photons on said photodetector;counting, during a period T, which is between 2 and 6 times a transfer time (Te), the number and location of the first detected non-scattered photons;determining the diameter and the position of a disk defined by a set of first non-scattered photons;determining the position (X, Y) of a scintillation event from the location of said first detected non-scattered photons;counting the number of the first detected non-scattered photons inside said disk during a period Td greater than a decay time (T) of the scintillator;defining the energy of a gamma photon, said energy being proportional to the number of non-scattered photons counted inside the disc. The invention also concerns the associated detection system, the microelectronic component and a scintillator crystal treated for use in a PET application, and the use of the detection system according to the invention in PET and SPECT imagers.

Method and apparatus for distinguishing radionuclide by using plastic scintillator

A method and an apparatus for distinguishing radionuclides are disclosed. The method comprises the steps of: receiving energy generated in one or more radioactive elements; applying energy as a weight for each channel to spectrum of the received energy; and distinguishing the one or more radioactive elements on the basis of the spectrum of the spectrum to which the weight is applied. A radioactive element having an energy value corresponding to a peak value of the spectrum of the energy to which the weight is applied, as an energy value of a Compton edge, is distinguished as the one or more radioactive elements. According to the present invention, it is possible to more accurately monitor radiation even while using a plastic scintillator, and further to improve energy resolution of a plastic scintillator.

ENERGY SEPARATION IN MULTI-ENERGY COMPUTED TOMOGRAPHY
20190083053 · 2019-03-21 ·

In accordance with the present approach, a kV switched X-ray source, such as a kV switched X-ray tube, is used in conjunction with a dual-layer detector. In such approaches, the dual-layer detector may be operated so as to ignore or discard signal attributable to low-energy photons generated during a high kV emission interval or view.

Gamma spectral analysis

Aspects of the subject technology relate to performing gamma spectral analysis based on machine learning. Gamma spectrum data, which can be associated with a gamma spectrum can be gathered. The gamma spectrum data can include an energy channel and a count rate for gamma rays detected by one or more gamma detectors. A spectral image can be constructed based on the gamma spectrum data. One or more machine learning models can be trained based on the spectral image. Additionally, one or more features of the gamma spectrum can be extracted from the spectral image through the one or more machine learning models.

INDIRECT PHOTON-COUNTING ANALYTICAL X-RAY DETECTOR
20190056514 · 2019-02-21 ·

An indirect, photon-counting X-ray detector capable of detecting the low-energy X-rays includes a scintillator screen that is directly coupled to a two-dimensional optical sensor. A signal filter receives an electrical output signal from the optical sensor and removes high intensity signal contributions therefrom that are indicative of direct interaction between said X-ray signal and said optical sensor. The scintillator screen has a sufficient thickness to ensure a high absorption of incident X-ray photons, and uses phosphor grains with a relatively small grain size. A cooling apparatus in thermal communication with the optical sensor may be used to control its temperature. The signal filter maintains a running average of changes in measured pixel output values for consecutive measurements, and replaces a measured value caused by a direct interaction event with a value equal to a previous measured value plus said running average.

RADIATION IMAGE CAPTURING SYSTEM
20190042876 · 2019-02-07 ·

A radiation image capturing system includes a plurality of radiation image capturing apparatuses that each performs an image capturing operation to capture a radiation image based on radiation emitted from a radiation generating apparatus and transmitted through an object, a control apparatus that communicates with the plurality of radiation image capturing apparatuses, a calculation unit that calculates information about similarity between the radiation image and a reference image, and an image acquisition unit that acquires the radiation image from the radiation image capturing apparatus selected from the plurality of radiation image capturing apparatuses based on the information about similarity.