46 results about "Radionuclide" patented technology

The invention relates to the technical field of medical instruments, and discloses a breast cancer sentinel lymph node positioning system and method, and the system comprises a data collection subsystem, a space positioning subsystem and a central processing subsystem. The method comprises the following steps: acquiring an anatomical structure image, a radioactivity counting rate and fluorescence intensity after performing primary fluorescence, radioactivity and secondary pulse type fluorescence tracer injection in sequence; establishing a global coordinate system and generating an anatomical region of interest; constructing a weighted directed topological graph based on the initial fluorescence data, and obtaining a baseline flow velocity; extracting radionuclide dynamic characteristics based on the radioactive data; a functional flow rate attenuation coefficient is calculated based on the second pulsed fluorescence data. And a multi-factor scoring model is applied, topological information, dynamic characteristics and functional flow velocity attenuation coefficients are fused, and a comprehensive score is calculated to identify the sentinel lymph node. According to the method, the lymphatic flow topological structure, nuclide dynamics and functional flow velocity information are combined, and the positioning accuracy and reliability are improved.

A detector system for molecular imaging of a radionuclide comprises a 3D semiconductor detector comprising a plurality of sensor stacks of sensors made of a semiconductor material having an average atomic number Z below 40. A read-out circuitry connected to the pixels is configured to output, for each interaction induced by an incident gamma ray in the detector, a signal representative of a time, a position and an energy of the interaction in the detector. The interactions in the detector belonging to a same event induced by the incident gamma ray are predicted based on the output signals and used to estimate a direction of the incident gamma ray and reconstruct an image based on the estimated directions of incident gamma rays.

The invention provides a radioactive internal pollution detection method and system based on a dynamic efficiency scale, and the method comprises the steps: carrying out the detection of the radioactive internal pollution based on a pre-obtained change table of the total detection efficiency of a detector for the radionuclide in a human body along with the time; determining the total detection efficiency of the radiation detector on the radionuclides in the human body according to the interval time and the types of the radionuclides; and obtaining the activity of the internal pollution radionuclides based on the characteristic gamma ray full-energy peak counting and the total detection efficiency of the radiation detector on the radionuclides in the human body. In-vivo metabolism behaviors of nuclides are considered, so that the internal pollution detection accuracy is greatly improved. The problems that in the prior art, equipment is large in size, high in manufacturing cost, long in measurement time consumption, complex in operation and the like are solved. The method is suitable for rapid detection and classification of mass personnel in nuclear and radiation accident emergency sites.

The present application relates to radionuclide separation and purification technical field, specifically disclose a kind of separation and purification method for preparing lead-212 and actinium-225 by photo nuclear reaction method.It includes the following steps: radium target solution is sequentially passed through lead resin column and DGA resin column, and recovery liquid is obtained;First eluent is used to elute lead resin column, and lead-212 first purification liquid is obtained;Second eluent is used to elute DGA resin column, and actinium-225 first purification liquid is obtained;Lead-212 first purification liquid is introduced into first LN resin column, and third eluent is used to elute first LN resin column, then third desorption liquid is introduced into first LN resin column, and lead-212 second purification liquid is obtained;Actinium-225 first purification liquid is introduced into second LN resin column, and fourth eluent is used to elute second LN resin column, then fourth desorption liquid is introduced into second LN resin column, and actinium-225 second purification product solution is obtained.The present application effectively avoids the cumbersome operation steps such as medium conversion, improves the separation and purification efficiency of lead-212 and actinium-225 in radium target.

The invention discloses a radiation hazard source identification method with a low counting rate, and relates to the technical field of nuclear technology application. Comprising the following steps: establishing a nuclide library containing radionuclide information; setting a peak position interval corresponding to each radionuclide based on the nuclide library; carrying out statistics on the peak position count of the peak position interval and the high-energy area count of the high-energy area, and caching the peak position count and the high-energy area count obtained through statistics as environment background data; estimating parameters according to the cached environment background data; acquiring a peak position counting rate and a high-energy region counting rate in real time; according to the parameters, the peak position counting rate and the high-energy region counting rate which are obtained in real time, the probability that the peak region is abnormal is calculated; performing early warning sequential test on the abnormal probability of the peak region; and comparing a result of the early warning sequential test with a preset early warning threshold value, and if the result reaches the early warning threshold value, outputting early warning information and identifying a corresponding radiation hazard source. According to the invention, rapid early warning and hazard source identification of abnormal radiation data are realized.

Disclosed are compounds represented by the following structural formula (I): or a pharmaceutically acceptable salt thereof. The variables of structural formula (I) are described herein. The compound of the invention can be attached to chelating groups for radionuclide binding and are therefore suitable for radioimaging and / or radiotherapy applications, for example the disclosed compounds can be radiolabeled with a positron emitter such as 18F, 68Ga or 64Cu, and used for positron emission tomography (PET). Alternatively, the compounds can be radiolabeled with an alpha particle emitter such as 223 Ac, a beta particle emitter such as 67Cu or 177Lu, or an Auger electron emitter (e.g. 111In, 67Ga, 99mTc, 195mPt, 125I, 123I and 161Tb) for use as a radiotherapeutic.

The invention discloses a double-target small-molecule probe, a radionuclide-labeled double-target small-molecule probe as well as a preparation method and application of the radionuclide-labeled double-target small-molecule probe. The medicine < 68 > Ga-DOTA-PRE / RGD is obtained by labeling < 68 > Ga radionuclide, and is applied to PET / MR (positron emission tomography / magnetic resonance imaging) imaging of pancreatic cancer tumors. A radioactive product with high purity and high stability (greater than 93%) is obtained through a simple marking method; the obtained double-target radioactive small molecular probe 68Ga-DOTA-PRE / RGD has a huge potential for the accurate diagnosis of pancreatic cancer.

The invention relates to the technical field of radioactive separation control, and discloses an intelligent switching control method and system for a multi-way valve in radionuclide separation, and the method comprises the steps: 1, pushing inert liquid, calibrating the dead volume of a liquid outlet section, and determining the quantitative line cleaning volume and the pre-charging volume of a target channel; step 2, advancing the pre-wetting liquid according to a preset pre-wetting volume and a pre-filling volume of a target channel; 3, pushing the feed liquid according to the loading volume, and executing a safe flushing volume according to a pressure signal; 4, purging the first leacheate and the second leacheate according to the quantitative line cleaning volume; 5, collecting an activity signal to generate an activity window entering signal and an activity window exiting signal; 6, responding to the signal, and switching to a target collection channel according to the isolation section volume, the quantitative line cleaning volume and the target channel pre-charging volume; and 7, cleaning and purging are conducted, the default safety position is reset, and the accumulated propelling volume of the pump is recorded. According to the invention, quantitative and sequential management of flow path switching in the radionuclide separation process is realized.

An image acquisition apparatus includes a measurement unit and a processing unit. The processing unit, for each coincidence event in which a first detector and a second detector perform coincidence detection of a pair of gamma-ray photons generated by an electron positron annihilation event in a positron emitting radionuclide, assuming that the gamma-ray photon arriving at one detector is a gamma-ray photon arriving without being Compton scattered in a subject, and the gamma-ray photon arriving at another detector is a gamma-ray photon arriving after being Compton scattered in the subject, determines a position at which the gamma-ray photon is Compton scattered in the subject based on a detection position and a detection time of the gamma-ray photon by each of the first detector and the second detector and a position of the positron emitting radionuclide.

A detector system for molecular imaging of a radionuclide comprises a 3D semiconductor detector comprising a plurality of sensor stacks of sensors made of a semiconductor material having an average atomic number Z below 40. A read-out circuitry connected to the pixels is configured to output, for each interaction induced by an incident gamma ray in the detector, a signal representative of a time, a position and an energy of the interaction in the detector. The interactions in the detector belonging to a same event induced by the incident gamma ray are predicted based on the output signals and used to estimate a direction of the incident gamma ray and reconstruct an image based on the estimated directions of incident gamma rays.

This invention relates to the field of radionuclide detection technology, and more particularly to a portable nuclide identification system based on an array-type CZT detector. The system includes a detector bias high-voltage establishment module, a raw energy spectrum acquisition module, a high-voltage power failure emergency protection module, an analysis thread module, and an energy spectrum UI display module. It achieves uniform high-voltage rise and fall and precise voltage stabilization through PID control, providing a reliable bias for the CZT detector. Simultaneously, it combines an array-type CZT detector with a dedicated ASIC readout circuit to complete high-precision conversion of gamma-ray energy and data verification and transmission. It also accumulates and stores energy spectrum data in real time and enables seamless power switching and soft-voltage shutdown, ensuring hardware, software, and data security. The analysis thread module performs preprocessing, peak fitting, intelligent disassembly of overlapping peaks, and branch ratio verification to complete qualitative identification of nuclides and quantitative analysis of activity concentration. Furthermore, it achieves smooth energy spectrum display through LTTB algorithm downsampling and supports touchscreen interaction and real-time nuclide information annotation.

The application discloses a radioactive separation laboratory environment radiation field dynamic modeling method and system, and belongs to the field of chemical process modeling. Step 1, the concentration distribution of a non-radioactive process tracer physically associated with a target radionuclide in a process fluid is obtained; step 2, based on the concentration distribution and the macroscopic residence time distribution of the material, the pre-judgment source term of the radionuclide is obtained through time translation and decay scaling; step 3, the radiation field observation waveform collected by a heterogeneous radiation sensitive field sensor network and independent of the pre-judgment source term is obtained; step 4, the theoretical radiation field change waveform calculated based on the pre-judgment source term is obtained; the application can obtain the concentration distribution of the non-radioactive tracer physically associated with the target radionuclide, eliminate the inherent bias of the source term from the source, and accurately depict the time-varying characteristics of the source term caused by the continuous migration of the material without making steady-state or quasi-static simplification assumptions on fluid turbulence, two-phase interface dynamic change and other processes.

A structure and process for containing a nuclear reaction is disclosed. The structure and process may involve a nuclear containment structure including a plurality of metallic rings stacked axially to form the nuclear containment structure, the nuclear containment structure being configured to: mitigate, by using a physical barrier, the movement of radionuclides from inside a containment structure to a surrounding space; shield, by varying the alloy properties throughout the containment structure, an exterior of the containment structure from radiation produced inside of the containment structure; regulate, by transferring thermal energy, a temperature within the containment structure; regulate, by storing thermal energy, the temperature within the containment structure; shield, components within the nuclear containment structure from kinetic events external to the nuclear containment structure; and shield, the external environment, from kinetic events within the nuclear containment structure.

The invention discloses a method for solidifying radionuclide technetium in a solution and application of the method, and belongs to the technical field of spent fuel post-treatment. The curing method comprises the following steps: firstly, acidifying a technetium-containing solution by using nitric acid, then adding the acidified technetium-containing solution into a sodium metaaluminate solution, and reacting under a low-temperature condition to ensure that technetium is covalently bonded with high-activity mu < 1->-OH in a curing product in a form of pertechnetate (TcO4 <->) and is cured in pseudo-boehmite-like mixed crystals with stable crystal structures; the curing method is mild in operation condition and simple in technological process, overcomes the defects that in a traditional cement curing and glass curing method, the size of a cured product is increased, technetium is prone to volatilization and the like, has the advantages of being small in cured product size, high in curing efficiency, low in cost and environmentally friendly, the maximum curing amount can reach 100 mg / g, and the curing method is suitable for industrial production. The method is suitable for treating technetium-containing acidic nucleus waste liquid generated in the spent fuel post-treatment process.

The utility model relates to a radionuclide treatment patient urine collection and temporary storage device which comprises a funnel-type collector arranged on a portable pedestal pan, a urine temporary storage tank is arranged below the funnel-type collector, the urine temporary storage tank is composed of an inner barrel body and an outer protective sleeve, a funnel opening in the lower end of the funnel-type collector can be inserted into the inner barrel body, and the outer protective sleeve can be inserted into the funnel opening in the lower end of the funnel-type collector. Urine of a patient subjected to nuclide treatment is collected in the inner barrel body, protection of different radionuclides in the urine is achieved through the outer protection sleeve, the upper face and the lower face of the outer protection sleeve are provided with structures capable of being connected and positioned respectively, and multiple urine temporary storage tanks can be stacked up and down in multiple layers. The temporary storage tank is suitable for temporarily storing treatment nuclides emitting pure beta particles, such as 90Y, or treatment nuclides emitting beta particles accompanied by low-energy gamma rays, such as 177Lu and 161Tb. According to the utility model, a new treatment project can be carried out under the environment-friendly condition for a medical unit for developing radionuclide tumor treatment when the capacity of the decay pool is insufficient or no decay pool exists, so that the number of treated patients is increased.

Systems, methods, and devices provide data correction for positron emission tomography (PET) examinations using an external, supplemental radioactive source. The supplemental radioactive source is formed of a uniformly distributed radionuclide. The uniformly distributed radionuclide is positioned in a support structure which is positioned into an inner bore of a PET scanner and secured in place by a friction fit, or directly integrated into the PET system. A transmission source control system moves the one or more 2024 / 059537 transmission sources into the support structure for performing the PET examination (e.g., using a hydraulic system). The transmission source control system also retracts the one or more transmission sources back into a source storage device upon completing the PET examination. Various data correction algorithms use the first PET signal data, originating from a radiotracer injected in the patient, and second PET signal data, originating from the uniformly distributed radionuclide.

The utility model discloses a nuclear power plant pipeline deposition source item simulation body, this nuclear power plant pipeline deposition source item simulation body includes closure, radiation source suction accessory and pipeline, radiation source suction accessory adsorbs multiple radionuclide of gamma ray energy 59.5keV-1332.5keV to be closed in closure, the closure is pasted in the inner surface of pipeline, the utility model discloses can simulate the deposition source item of pipeline inner surface through the closure of radiation source suction accessory, the closure of radiation source suction accessory is pasted in the inner surface of pipeline, can be used to simulate the condition of the consistent deposition source item of pressurized water reactor primary loop pipeline in the pipeline, is used to confirm the active efficiency scale of deposition source item measurement, greatly reduces the risk of radioactive contamination in the active efficiency scale process.

The invention discloses a radioactive separation laboratory environment radiation field dynamic modeling method and system, and belongs to the field of chemical process modeling, and the method comprises the steps: 1, obtaining the concentration distribution of a non-radioactive process tracer agent which is in a physical associated relationship with a target radionuclide in a process fluid; step 2, based on the concentration distribution and the macroscopic retention time distribution of the material, obtaining a prejudgment source item of the radionuclide through time translation and scaling according to decay; step 3, acquiring a radiation field observation waveform which is acquired by the heterogeneous radiation sensitive field sensor network and is independent of the pre-judgment source item; 4, changing the waveform of the theoretical radiation field calculated based on the pre-judgment source item; according to the method, the non-radioactive tracer physically associated with the target radionuclide can be adopted to obtain the concentration distribution, steady-state or quasi-static simplified assumption does not need to be made in the processes of fluid turbulence, two-phase interface dynamic change and the like, the inherent deviation of the source item is eliminated from the source, and the time-varying characteristic of the source item caused by continuous migration of the material is accurately described.

The invention relates to a device (101) for detecting a radionuclide in a gas, the device comprising: - a scintillation unit (1) configured to contain the gas, the scintillation unit (1) comprising a porous inorganic scintillator (2) and a container (3) containing the porous inorganic scintillator (2) and comprising at least one portion which is transparent to the photons emitted by the scintillator (2) due to disintegrations of the radionuclide, the container (3) comprising at least one opening (7, 8) for the entry and exit of the gas and for causing it to circulate through the scintillator (2); - detection means (9, 10) configured to detect photons emitted by the porous inorganic scintillator (2); and - an enclosure (12) opaque to photons external to the enclosure (12), which allows the entry and exit of the gas and in which the scintillation unit (1) and the detection means (9, 10) are arranged, the opaque enclosure (12) comprising an opening / closing system and being openable and reclosable so as to allow access to the scintillation unit (1).

This utility model discloses a radionuclide separation device for radioactive waste liquid, comprising a separation device body, a precipitation chamber, and an ion exchange column. The precipitation chamber is located at one end of the separation device body, and a metering cylinder is located at the top end of the separation device body. A piston pusher plate is installed inside the metering cylinder, and a cylinder is fixed to the top of the metering cylinder. The output end of the cylinder is connected to the piston pusher plate via a telescopic rod. An ion exchange column is located inside the separation device body on one side of the precipitation chamber. This utility model, by installing a separation device body, a filter box, a precipitation chamber, a first drive motor, a stirring component, a metering cylinder, a cylinder, a piston pusher plate, a discharge pipe, and a solenoid valve, controls the amount of chemical reagent introduced, quantitatively adding reagent to ensure sufficient reaction between the radionuclides in the waste liquid and the chemical reagent, thereby improving separation efficiency.

This application relates to the field of ECT imaging technology, and provides a method, apparatus, and system for configuring nuclide information in an ECT imaging system. This allows for the automatic configuration of new nuclides within the ECT imaging system, improving the efficiency and accuracy of new nuclide configuration. This application acquires basic information about the target nuclide, including its name and half-life. Based on the nuclide name and half-life, it controls the detector in the ECT imaging system to acquire data for a set acquisition duration, obtaining energy spectrum distribution data of the target nuclide at that set acquisition duration. Based on the energy spectrum distribution data, it obtains parameter configuration information for the target nuclide. Finally, it configures the target nuclide in the ECT imaging system according to the parameter configuration information.

This invention discloses a covalent organic framework material, its preparation method, and its application, belonging to the technical field of radionuclide processing materials. This COFs serves as... 131 I ‑ The application of the removal material specifically includes: mixing COFs with a guest molecule solution; and removing Na... 131 Add aqueous solution to the above solution, let stand under light, centrifuge, and collect COFs to achieve the determination of COFs in the solution. 131 I ‑ Removal; This COF material, driven by guest molecules, significantly increases singlet oxygen production, thereby enhancing oxidation. 131 I ‑ This material possesses the ability to generate I2, achieving highly efficient adsorption and photocatalysis of radioactive iodine ions. It is economical, environmentally friendly, and stable, suitable for various applications, and provides a novel solution for designing efficient reactive oxygen species generation and adsorption of radioactive iodine-131 ions.

The utility model relates to the technical field of nuclear radiation, in particular to a neutron angle correlation distribution information acquisition system, which comprises a neutron detector, a time position sensitive detector module, a time flight measurement module, a synchronous trigger control module, a signal processing module, a data acquisition module and a spherical support frame, the system adopts a structure in which multiple neutron detectors are uniformly distributed, is combined with a time position sensitive detector module and a time flight measurement module, is distributed on a spherical framework, and can collect neutron angle correlation distribution in a 4pi space angle, including neutron energy, time and angle; and angle distribution, time difference distribution, energy association, event counting and direction association information are obtained, and data information support is provided for radionuclide identification.

This invention provides a method for preparing a proximity irradiation therapy source. [Solution] A method for accumulating radium radionuclides, comprising the steps of: providing a first solution containing a thorium radionuclide and a thorium-binding extractant, wherein the first solution is not bound to radium; decaying a portion of the thorium radionuclide in the first solution into radium atoms; and collecting the radium atoms resulting from the decay. The collected radium atoms may be included in a solution into which a proximal irradiation source is immersed, in a manner that collects the radium atoms into the proximal irradiation source.

The application discloses a water-based wide-temperature-range scintillation liquid compounding system, a radioactive detection method and a sensor, and the system is composed of a scintillator, nonionic, anionic and zwitterionic surfactants, a cosolvent, a solvent and water; by regulating the polymerization chain length of the nonionic surfactant, the HLB value is accurately controlled, the surface tension is optimized, and the efficient connection of the scintillation phase and the radionuclide water phase is realized; the anionic surfactant reduces the interfacial tension, and ensures the uniform dispersion of components; the zwitterionic surfactant dynamically adjusts the HLB value through the dissociation degree of the charge group, and the dissociation degree of the charge group can change with temperature, and the micelle structure stability is dynamically adjusted in a wide temperature range. The scintillation liquid has excellent detection efficiency and extremely low detection limit, and has outstanding water containing performance and temperature adaptability, and brings more efficient and accurate technical support to the field of radioactivity detection.

Method for characterizing an object comprising at least one radionuclide emitting beta radiation, the method comprising: - placing a detector facing the object; - detecting the radiation emitted by the object; - forming, from the radiation detected by the detector, an input spectrum comprising a beta component; - applying to the input spectrum an identification algorithm associated with a radionuclide, the identification algorithm determining the presence in the object of the radionuclide associated with the identification algorithm; - identifying, from d), the radionuclide contained in the object; - applying a deconvolution algorithm to the input spectrum in order to estimate the contribution of each radionuclide identified in e) to the input spectrum.

The invention discloses a radioactive urine source treatment system and method, and belongs to the technical field of medical waste treatment and nuclear radiation protection. The system comprises a vacuum separation type closestool, a urine temporary storage and conveying unit, a multi-path parallel filtering unit with at least two parallel branches, a multi-point state monitoring unit and a control system. The working method comprises the following steps: urine is separated by a closestool, enters the temporary storage unit under the action of negative pressure, is guided into the selected filter branch, and is sequentially treated by the multi-stage filter columns filled with the composite functional material to efficiently adsorb radionuclides. The monitoring unit collects the radiation dose of the filter element and the radioactive level of the discharged water in real time, and when the filter element is close to saturation or the discharged water exceeds the standard, the control system is automatically switched to the standby branch and gives an alarm to prompt replacement of the saturated filter element. According to the system, real-time purification from the source, full-process automatic control and uninterrupted operation are realized, the problems of large occupied area, high cost and potential safety hazards of a traditional decay tank are avoided, and the treatment efficiency and the operation safety are remarkably improved.

Title: HIGH-INTENSITY MULTI-PARTICULAR CYCLOTRON FOR THE INDUSTRIAL PRODUCTION OF α AND β- RADIONUCLIDES. The invention relates to a cyclotron for the production of α or β- emitting radionuclides. The cyclotron, with a magnetic periodicity of 3, comprises three accelerating cavities connected at the center, thus eliminating the need for phase control between the cavities, forming a single high-frequency resonator. The 6 accelerating spaces per revolution allow for rapid acceleration (the angle ϕ between the accelerating spaces of each cavity is approximately 30°), essential for acceleration in the 3rd and 6th harmonics. This cyclotron preferably has an injection system (31) powered by various types of ion sources, enabling the efficient acceleration of charged particles with Z / A ratios of 1 / 2 and 1 / 4.The cyclotron can also be equipped with stripping extraction devices positioned within it to extract charged particles and double their charge state. These particles allow for the execution of a range of nuclear reactions for the production of α- and β-emitting radionuclides. See Figure 4B for the abbreviation.

The invention provides a nuclear medical radioactive wastewater treatment system and method.The system comprises a pre-precipitation chamber, a buffer chamber, an adsorption chamber, a sewage decay chamber and a sludge decay chamber, two sets of baffles are arranged in the pre-precipitation chamber and divide the pre-precipitation chamber into three cavities, the baffles can prevent large-size solids in wastewater from entering the next pre-cavity, and therefore the large-size solids in the wastewater can be prevented from entering the next pre-cavity; large-size solids naturally precipitate to the bottoms of the chambers and are discharged into the sludge decay chamber, wastewater can enter the next chamber after penetrating through a gap in the middle of the baffle, adsorption, flocculation and precipitation are completed after the wastewater enters the adsorption chamber through the buffer chamber, and radionuclides are separated into sludge from the wastewater through solid-liquid separation. In subsequent treatment, only a small amount of sludge containing radionuclides needs to be discharged into the sludge decay chamber for long-time storage decay, and a large amount of separated wastewater is discharged into the sewage decay chamber for short-time storage and can be directly discharged, so that the use efficiency of the decay tank is greatly improved. The method has the advantages of simple process flow and less secondary waste, and realizes efficient volume reduction and rapid purification treatment of nuclear medical radioactive wastewater.

The present invention provides brachytherapy radiation delivery device designed to topically treat cutaneous skin lesions in patient tissue. The topical radiation delivery device includes a layer of one or more radionuclides. The topical radiation delivery device includes a high Z top shielding layer placed adjacent the side of the radionuclide layer away from the patient tissue. The top shielding layer attenuating the energy of the radionuclide from the environment external to the patient. The patch further includes a bolus layer placed between the patient tissue and the radionuclide layer which attenuates the beta radiation fluence. The one or more radionuclides of the brachytherapy radiation delivery device producing a gamma and beta radiation fluence to achieve a desired Percent Depth Dose within the cutaneous skin lesion.