16 results about "Half-life" patented technology

This invention provides a target loading device for producing short-half-life isotopes in a heavy water reactor, comprising a channel, an electric cylinder, and a target drum assembly. One end of the channel leads to the reactor core. The target drum assembly sequentially pushes the loaded targets to the target outlet. The main shaft of the electric cylinder is coaxially arranged with the target outlet, driving the main shaft to move towards the target outlet to push the target at the outlet into the channel. The target enters the reactor core through the channel. This invention enables the loading of short-half-life radioactive isotope targets for several days or tens of days during heavy water reactor power operation, facilitating installation and maintenance. Different types and quantities of isotope targets can be loaded into the core production channel during heavy water reactor power operation.

The invention relates to the technical field of science popularization demonstration, in particular to a half-life period demonstration device and a half-life period demonstration method. The device comprises a base body, a plurality of vertically-arranged demonstration cavities are formed in the table top of the base body, magnetic jumping blocks are arranged in the demonstration cavities, the visual states of the top faces and the bottom faces of the magnetic jumping blocks are different, and the magnetic pole directions of the top faces and the bottom faces of the magnetic jumping blocks are opposite; an electromagnet is arranged under each magnetic jumping block, all the electromagnets can be controlled by a controller to switch the magnetic pole direction, and when the controller controls part of the electromagnets to switch the magnetic pole direction, the part of the electromagnets and the bottom faces of the magnetic jumping blocks are magnetically repelled to drive the magnetic jumping blocks to jump and turn over. Therefore, radioactive decay of part of atomic nucleuses in the elements is demonstrated. According to the invention, by combining the action of a mechanical structure, the nuclear decay process and rule can be dynamically and visually displayed, so that the double problems of non-visual teaching and weak science popularization display can be solved.

Nuclear emergency 131 I Isotope measuring device and its remote calibration method, the method at least includes: in the standard environment: to 131 I Isotope at least two distance conditions of detection efficiency measurement, and establish 131 I Isotope and the detection efficiency relationship of the first reference isotope;In the remote calibration site and in the condition of energy calibration: measure the measured detection efficiency of one of the distance conditions of the first reference isotope with known activity, and determine 131 I Isotope measured detection efficiency in at least one distance condition;Compare 131 I Isotope measured detection efficiency with the corresponding detection efficiency is consistent or not.The present application completes the remote calibration of 131 I Isotope measuring device by using the reference isotope with long half-life and the detection efficiency relationship of the reference isotope and 131 I Isotope, without transporting high activity standard source to the site, solves the problem that 131 I Isotope is not easy to save due to short half-life.

The invention relates to compounds according to Formula (I):wherein A is—As(OH)2 or an arsenoxide equivalent group; each of R1, R2, R3 and R4 is independently selected from H, X, OH, NH2, CO, SCN, —CH2NH, —NHCOCH3, —NHCOCH2X or NO, and X is a halogen; R5 is —NHCH2COOH, OH or OR6, wherein R6 is a C1-5 straight or branched alkyl group; and Z is a radioisotope with a half-life of less than 4 days, or a pharmaceutically acceptable salt, ester, prodrug or solvate thereof, uses of said compounds, and methods of preparing said compounds. The invention also relates to diagnostic methods utilizing said compounds.

The invention discloses a source item inversion optimization method and system for nuclide with a long half-life period. The method comprises the following steps: determining a nuclear accident source item and meteorological parameters influencing nuclear accident source item inversion; based on the contribution degree of multiple nuclides to the environmental dose rate, adjusting the release rate change gradient of long-life nuclides with low contribution degree to the environmental dose rate so as to enhance the recognition capability of the long-life nuclides in dose rate inversion; simulating a nuclear accident scene, and generating a training data set and a test set required by the neural network model; performing data preprocessing on the meteorological parameters, the environmental dose rate and the nuclide release rate; determining a neural network model with time sequence analysis capability, and building a nuclear accident source item inversion model; determining a hyper-parameter optimization method of the neural network model, and optimizing hyper-parameters of the neural network; and testing the nuclear accident source item inversion model by using the test set to obtain an optimal nuclear accident source item inversion model. According to the method, the inversion error of the low-contribution nuclide is remarkably reduced, and higher robustness and practicability are achieved.

The present invention relates to a method of determining the half-life T1 / 2 of a biomolecule of interest, said method comprising: (a) bringing said biomolecule into contact with a compound that decreases the amount of said biomolecule; (b) determining the amount of said biomolecule as a function of time; (c) determining, from amount as a function of time, (i) the half-life T1 / 2* of said biomolecule upon said bringing into contact; and (ii) the ratio r of the equilibrium amount of said biomolecule in the presence of said compound over the equilibrium amount of said biomolecule in absence of said compound; and (d) determining said half-life as T1 / 2 = T1 / 2* / r.

The application provides a nuclide identification method and device, comprising: obtaining gamma spectrum data of a target radioactive source; determining whether other characteristic peaks except for specified characteristic peaks are contained in characteristic peaks of the gamma spectrum data; if yes, determining a first peak area corresponding to the other characteristic peaks and a second peak area of the specified characteristic peaks according to the gamma spectrum data; determining a total area of the specified characteristic peaks contributed by all nuclides of the target radioactive source according to the first peak area and a peak branch ratio of each first nuclide; determining whether the second nuclide having only the specified energy peak value is contained in the target radioactive source according to the second peak area and the total area; if yes, determining the second nuclide in the target radioactive source through half-life measurement; and determining the nuclide composition of the target radioactive source according to the first nuclide and the second nuclide. The method can identify the heavy peak by setting the verification condition, and then determine the nuclide composition, so that the technical problem of nuclide missing identification can be relieved.

This invention relates to the field of isotope production using the vertical flux detector channel of a heavy water reactor. Addressing the problems of inefficient isotope production using the vertical flux detector channel of a heavy water reactor, and the simultaneous production of multiple isotopes, this invention provides a target for isotope production using the vertical flux detector channel of a heavy water reactor. Several inner target tubes are arranged inside an outer target tube. The outer target tube has upper and lower end plugs at both ends. A metal wire is attached to the upper end plug to allow the target to enter or exit the reactor core through the vertical flux detector channel. The inner target tubes are loaded with at least one target material to produce at least one isotope. This invention has a simple structure, is easy to manufacture, and can achieve mass production of short-half-life medical isotopes such as lutetium-177, strontium-89, and holmium-166 using the vertical flux detector channel of a heavy water reactor.

The invention discloses a method and a device for simultaneously preparing multiple isotopes. The method comprises the following steps: bombarding a conversion target into a secondary radiation beam by using a high-energy particle beam; carrying out irradiation treatment on the composite target piece by adopting a secondary radiation beam; respectively separating and purifying each sub-target piece of the composite target piece to obtain targeted nuclides; the method comprises the following steps: setting corresponding cooling time for similar isotope material targets according to nuclide half-life periods, preferentially performing radiochemical separation and purification on nuclides with short half-life periods, and then performing separation and purification on targeted nuclides with relatively long half-life periods; according to the invention, a composite target is selected according to a target nuclide, and secondary radiation is generated through collision of high-energy particles on a conversion target; during irradiation, the irradiation sequence of different types of target pieces is adjusted, and different target nuclides are obtained through primary bombardment of secondary radiation photons; after similar isotope material targets are irradiated, separation and purification processes are respectively carried out according to different half-life periods of target nuclides, different nuclides are obtained, and multiple isotopes are simultaneously prepared through one-time irradiation.

The invention relates to the technical field of radioactive isotope preparation, and discloses a high-purity terbium-149 separation preparation method and system based on an electromagnetic mass spectrometry tandem separation technology, and the method comprises the following steps: bombarding a 151Eu target material based on an alpha beam to obtain an irradiated target material of the 151Eu target material, and carrying out high-temperature gasification on the irradiated target material to obtain the high-purity terbium-149. The method comprises the following steps: irradiating a target material to obtain nuclide steam of the irradiated target material, carrying out strong electromagnetic separation on isobaric elements of the nuclide steam to obtain a crude separation target product of the nuclide steam, and carrying out fine separation on the crude separation target product based on a pre-calibrated high-resolution mass spectrometer to obtain terbium-149 ions of the irradiated target material. Condensing and collecting the terbium-149 ions, and dissolving the terbium-149 ions into a medical-grade terbium chloride solution of the terbium-149 ions; according to the method, high-efficiency, high-purity, low-energy-consumption and short-process preparation of terbium 149 is realized, and the large-scale production requirements of targeted alpha therapy on high-purity and short-half-life alpha nuclide can be met.

The application provides an elution curve real-time analysis method and system for At-211 purification process, relates to the technical field of signal analysis, generates elution curve data by real-time sampling of continuous detection signals output by a chromatographic separation device, sets time constraints for elution determination and divides multiple determination time windows in combination with the radioactive half-life characteristics of At-211 and the allowed activity loss requirements; a reference elution baseline is constructed and updated during the elution process, the difference change of the elution curve relative to the reference elution baseline is analyzed, candidate elution state determination, effective elution interval determination and elution end determination are sequentially completed, and then the starting and ending collection time of the eluent is determined, so that the segmented collection control of the At-211 eluent is realized; the method can continuously determine the elution state within a controlled time range and is suitable for the purification process of radionuclides.

The present disclosure provides a high-energy, low toxicity radiopharmaceutical composition comprising actinium that performs as an anti-tumor agent for targeted radionuclide therapy. The radiopharmaceutical composition disclosed herein has a short physical half-life of about 9.9 days and produces low toxicity profiles.

The application discloses a kind of radioactive contaminated clothing intelligent management method and related equipment.The method comprises the following steps: collecting the initial radiation dose of the contaminated clothing and generation time;Based on the nuclide decay formula, a decay tracking calculation process is constructed, the current dose is calculated in real time according to the nuclide half-life parameter, and the total dose is obtained by superimposing the contribution of each nuclide when there is multi-nuclide contamination;The current dose calculated in real time is compared with the preset control threshold, and the washable instruction is pushed to the medical terminal when the control threshold is met, and the remaining decay time prompt is output when the control threshold is not met.It can solve the problem that the management of radioactive contaminated clothing is highly dependent on manual, which can easily lead to waste of manpower, missed or wrong recording, and occupational health hazards caused by frequent close contact of medical staff with high-activity contaminated clothing during manual monitoring.

The application provides a capability verification liquid sample stability test method and related equipment, and relates to the technical field of radionuclide analysis.The method comprises the following steps: randomly drawing a preset number of to-be-processed liquid samples from a liquid sample, determining a stability test parameter, placing the to-be-processed liquid samples into corresponding test environments for processing, obtaining to-be-tested liquid samples, and the stability test parameter at least comprising a temperature.An analysis is performed according to a standard analysis method to obtain a measurement average value of a radionuclide, the measurement average value is corrected to a preset test date according to a half-life of the radionuclide to obtain a corrected average value, and a stability conclusion of the liquid sample under the stability test parameter is obtained according to the corrected average value.The method can test factors affecting the stability of the capability verification liquid sample, avoid the influence of these factors during the analysis of the activity concentration of the radionuclide, and improve the reliability of the analysis result of the activity concentration of the radionuclide.

The invention provides an iodine-131 treatment patient discharge monitoring system, and the method comprises the steps: carrying out the initialization modeling, and generating an initial attenuation curve based on a physical half-life period; introducing a composite attenuation model containing double components of physical decay and biological metabolism; periodically receiving actually measured environment dose rate data reported by the patient terminal; performing intelligent dynamic calibration on metabolic component parameters in the composite model by using time sequence measured data to generate a personalized dynamic attenuation curve; predicting a future accumulated exposure dose based on the curve and performing risk assessment; customized closed-loop safety intervention is automatically executed according to an evaluation result, and the method relates to the technical field of medical health information technology and radiation protection, and realizes conversion from static general management to dynamic precise intelligent protection by deeply fusing a theoretical physical model, an individual physiological metabolism model and real-time monitoring data. And the accuracy, the initiative and the compliance of radiation safety risk management are remarkably improved.

The invention discloses a radiopharmaceutical dosage control system and method, and relates to the field of radiopharmaceuticals, and the control method comprises the following steps: S1, collecting inherent parameters of a medicine, obtaining real-time physiological parameters of a patient, and reading a preset threshold value of the system; s2, calculating the residual activity in real time based on a decay algorithm and the temperature data, and dynamically adjusting the drug flow rate according to the deviation with the target activity; s3, identifying the pipeline adsorption loss by comparing the upstream and downstream activity difference values, and dynamically adjusting the flow velocity compensation deviation; and S4, acquiring infusion key parameters and recording data, and meanwhile, sending an emergency stop signal to interrupt infusion. Through coupling calculation of an index rule of nuclide decay and a temperature influence coefficient, activity attenuation of radionuclides caused by time lapse and temperature change is automatically corrected, and the dosage accuracy of short half-life period medicine infusion is remarkably improved, so that hidden errors caused by environmental fluctuation or operation delay are reduced, and the safety of short half-life period medicine infusion is improved. And a core guarantee is provided for precise radiotherapy.