104 results about "Radionuclide" patented technology

The invention provides an off-site full-range radiation risk evaluation method and system under a severe accident of a nuclear power plant, and the method comprises the steps: S1, building a radioactive accident risk evaluation basic model architecture, adapting to a model demand, and building a corresponding basic database; s2, constructing radioactive smoke plume characteristics after the accident; s3, calculating accident site space gridding and smoke plume transmission discretization; s4, sampling meteorological conditions, and simulating smoke plume transmission; s5, calculating the radiation dose in the early stage of the grid domain, and carrying out risk assessment; s6, performing risk assessment on the health effect in the early stage of the grid domain; s7, calculating the medium-and-long-term stage radiation dose in the grid domain, and performing dose risk assessment; and S8, performing health effect risk assessment and accident consequence assessment in the medium-and-long-term stage. According to the method, the whole transportation process of the radioactive smoke plume under a serious accident is simulated, loss effects such as dry and wet settlement and radioactive decay of the smoke plume are considered, and the activity of the radionuclide deposited on the ground and retained in the air in the off-site space range is determined.

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.

A method of generating an emulsion for treating a patient. The method includes generating a water-based solution carrying an agent which turns into a hydrogel by addition of calcium ions. Radium radionuclides are added to the water-based solution in a concentration sufficient for radiotherapy. After adding the radium to the water-based solution, the water-based solution is mixed with an emulsifier and an oil.

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.

In a sodium-cooled fast reactor, a breached fuel pin releases fission and activation products into the primary sodium coolant and into the cover gas. A portion of the primary sodium coolant is diverted to a distillation system where its constituents can be separated based on volatility. Condensing these constituents enables precise measurement of their concentration without delays caused by waiting for the decay of radioactive sodium background scatter, enhancing the detection and quantification of the dilute constituents. Additionally, the method continuously determines the initial concentration of constituents in the feed. Quantification is achieved using detectors, facilitating the continuous assessment of dilute constituent concentrations in the sodium coolant feed stream.

The application discloses a rare earth nanoparticle-organic photosensitizer composite material and application thereof. By introducing rare earth doped nanoparticles as an energy conversion medium, direct activation of excited triplet states of an organic photosensitizer and sensitized production of singlet oxygen under excitation of radionuclides (e.g., 64Cu, 67Cu, 90Y, 111In, 177Lu, etc.) are realized. 18 F、 99m Tc、 177 Lu, etc.) excitation, the rare earth doped nanoparticles respond to CL and the rare earth ions reach an excited state after various high-energy radiation. Subsequently, through an interface energy transfer process, the excited state energy of the rare earth ions is directly transferred to the excited triplet state of the organic photosensitizer, and then singlet oxygen is generated, realizing tumor cell killing. The nanocomposite material is surface modified to load iRGD peptides to realize in vivo tumor targeting. 18 F-FDG (fluorodeoxyglucose) can realize tumor targeting through abnormal glucose uptake of tumors. The combination of the two realizes double targeting of in vivo tumors, and enhances the anti-tumor efficacy and safety.

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.

The invention relates to a method (10) for characterizing at least two radionuclides mixed in a radioactive fluid, the radionuclides being substantially pure beta emitters, the method (10) being carried out by a device (1) calibrated by an average number of photons detected per decay and a decay detection yield value for each radionuclide, the method comprising: measuring (14) an average number of photons produced per decay for the radioactive fluid, determining (16) a number of decays for each radionuclide from the average number of photons detected for each radionuclide and the average number of photons detected for the radioactive fluid, and determining (18) the activity of each radionuclide from the number of decays and the calibration value for each radionuclide. [Fig. 1]

Methods and apparatus are disclosed for concurrent digital autoradiography of alpha-particle events and positron events using a spatially resolving charged particle detector and a gamma-ray detector. Alpha particles and positrons are detected by the charged particle detector. Positrons are identified based on coincidence with gamma-ray events. A positron-emission autoradiograph is formed based on positron positions. Alpha particles, both coincident and anticoincident with positrons, are identified based on energy deposition patterns. An alpha-emission autoradiograph is formed based on alpha-particle positions and energies. Separation of coincident alpha and positron events recorded by the charged particle detector improves position detection accuracy. Validation of positron imaging for alpha-emitter distribution or dosage, based on correlation of respective autoradiographs, is described. Variations for particle identification based on isotropy, energy, coincidence, or anticoincidence are presented. Disclosed techniques are applicable to alpha-emitting radionuclides with complex decay chains.

Disclosed herein are methods for radiotherapy treatment plan optimization for irradiating one or more target regions using both an internal therapeutic radiation source (ITRS) and an external therapeutic radiation source (ETRS). One variation of a method comprises iterating through ITRS radiation dose values and ETRS radiation dose values to attain a cumulative dose that meets prescribed dose requirements. In some variations, an ITRS is an injectable compound that has a targeting backbone and a radionuclide, and images acquired using an imaging compound that has the same targeting backbone as the injectable compound can be used to calculate the radiation dose deliverable using the injectable ITRS, and also to calculate firing filters for delivering radiation using a biologically-guided radiation therapy (BGRT) system. Image data acquired from a previous treatment session may be used to adapt the dose provided by an ITRS and / or ETRS for a future treatment session.

A detector system (1) for molecular imaging of a radionuclide comprises a 3D semiconductor detector (100) comprising a plurality of sensor stacks (110) of sensors (120) made of a semiconductor material having an average atomic number Z below 40 A read-out circuitry (!26) connected to the pixels (125) is configured to output, for each interaction induced by an incident gamma ray in the detector (100), a signal representative of a time, a position and an energy of the interaction in the detector (100). The interactions in the detector (100) 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.

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.

A method of generating an emulsion for treating a patient. The method includes generating a water-based solution carrying an agent which turns into a hydrogel by addition of calcium ions. Radium radionuclides are added to the water-based solution in a concentration sufficient for radiotherapy. After adding the radium to the water-based solution, the water-based solution is mixed with an emulsifier and an oil.

The invention relates to wet preparation of a radiation therapy source and a method for accumulating radium radionuclides. The method comprises providing a first solution comprising a thorium radionuclide and a thorium binding extractant, wherein the first solution does not bind to radium; allowing a portion of the thorium radionuclides in the first solution to decay to radium atoms; and collecting radium atoms resulting from the decay. The collected radium atoms may be contained in a solution into which a brachytherapy source is immersed in a manner that collects radium atoms onto the brachytherapy source.

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 invention discloses a solid-state target system for producing multiple nuclides by multiple particles, and relates to the technical field of radionuclides. The target cavity is arranged on the right side of the accelerator; a combined target is arranged in the target cavity, and various radionuclides are generated after the combined target is irradiated by the accelerator; the fixing device is arranged in the target cavity, connected with the combined target and used for fixing the combined target; and the cooling system is connected with the target cavity and is used for cooling the combined target. The invention solves the problem of single type of nuclides produced by an accelerator in the prior art, and provides a solid-state target system for producing multiple nuclides by multiple particles.

The present application belongs to the field of radiation environment measurement, and particularly relates to a method for simulating radionuclide surface contamination wiping efficiency by using rhenium element 90 Sr- 90 Y research surface contamination wiping efficiency method. Through the radioactive characteristics of rhenium element, combined with radiation counting device for quantitative analysis, the present application can accurately evaluate the removal effect of radioactive contamination on different surface materials, and the present application provides a method for simulating and researching radionuclide surface contamination wiping efficiency by using non-radioactive element rhenium element 90 Sr- 90 Y surface contamination wiping efficiency method, reduces the use of radionuclide, is simple and easy to operate, is friendly and safe to personnel and environment, reduces research cost, has various material applicability and operability; the present application can accurately evaluate the removal effect of radioactive contamination on different sample materials, has wide applicability, and can provide technical support for actual scientific decontamination and cleaning work.

An electric generator can include: a radionuclide to emit gamma radiation (GR); an emitter having an emitter atom to receive the emitted GR so that, the GR causes an electron of an emitter atom to be liberated, and thereby be emitted from an emitter surface; a collector spaced from the emitter surface forming a gap between the emitter surface and a collector surface; and a gas having a gas atom and a gas pressure, in the gap, to receive, GR passed through the emitter so that, the received GR causes an electron of the gas atom to be liberated; wherein electrons liberated from the emitter atom and the gas atom are received by the collector, thereby causing an electrical potential difference between the emitter and the collector, and so that an electric current corresponding to a flow of electrons between the emitter and the collector is producible from the collector.

The invention relates to a device for producing radionuclides, in particular diagnostic and therapeutic radionuclides, on the basis of the principle of photo-nuclear radiation, comprising an electron accelerator (1), which generates an electron beam (2) with temporal structural features for the linear electron accelerator (1), a converter target assembly (21), which is arranged between the electron accelerator (1) and the converter target assembly (21), the invention relates to a converter target assembly (21) for generating radionuclides, comprising a converter target (20) for converting the electron beam (2) into bremsstrahlung photons (15), a plurality of production targets (17) irradiated by the bremsstrahlung photons (15) in order to generate the radionuclides, the converter target assembly (21) comprising a sealed housing (9) enclosing a cavity (19) accommodating the converter target (20), comprising an entrance window with a window disk (23) for the electron beam (2) and an exit window for the bremsstrahlung photons (15), comprising cooling medium ports (10) which are part of a cooling circuit (11) for establishing a cooling flow through the cavity (19) in order to cool the converter target (20) and the window disk (23), the converter target (20) comprises a plurality of rotatable converter discs (12), the electron beams (2) are arranged off-center with respect to the respective converter discs (12), and wherein the respective converter discs (12) are designed to rotate during operation of the device such that the converter discs (12) are arranged on the converter target (20) over time. The focus of the electron beam (2) is dispersed onto an annular region (14) of the converter disk (12) in multiple rotations.

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.

Irradiation targets, systems and methods are provided for producing radionuclides by irradiation of the target with ions from a particle accelerator. Irradiation targets comprise a metallic layer enriched with a specific metal isotope, a base plate supporting the metallic layer, and an isolating layer covering the metallic layer on the base plate by at most 3 μm of a deposited metal having a low vapor pressure. The base plate is made of a metal or metal alloy that has a high thermal conductivity, and the irradiation target is configured to be set within a case of an irradiation device that irradiates the metallic layer thereof with the ions. Methods and systems of producing the irradiation targets and processing the targets after their irradiation are further provided.

The invention provides a nuclide applicator and a preparation method thereof. The nuclide applicator comprises a source core frame, a source cover and a source window, the source core frame comprises a frame and a source core emitting beta rays through nuclide, a supporting table is arranged on the bottom face of the frame, the source core is formed on the supporting table, the source cover is arranged on the top face of the frame in a sealed mode, a handle is arranged on the top face of the source cover, and the source window is arranged on the bottom face of the frame in a sealed mode. And a source window protection tube is arranged on the bottom surface of the source window. The nuclide applicator is simple in structure, tight in sealing and high in safety, and has the advantages of being noninvasive, comfortable and convenient in treatment and the like in treatment of tumors, scars and skin diseases.

A system and method for treating radioactively contaminated water. An exemplary method comprises inputting the contaminated water into a treatment reservoir at an inlet of the treatment reservoir, the contaminated water containing a concentration of a beta-emitting radionuclide; irradiating the contaminated water in a treatment zone of the treatment reservoir with a treatment radiation from a photon delivery system, causing accelerated beta-decay of the beta-emitting radionuclide; and outputting treated water at an outlet of the treatment reservoir, the treated water containing the concentration of a decay product.

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.