53 results about "Radiogenic Isotopes" patented technology

A compound or molecular complex. The compound or molecular complex comprises: a metal chelator configured for chelation with a radioactive isotope or a non-radioactive isotope; and a trifluoroborate (BF3)-containing moiety configured for 19F / 18F exchange or a precursor thereof; and optionally a cell-targeting domain.

The invention relates to the cross technical field of nuclear reactor engineering and corrosion engineering, in particular to a radioactive isotope tracing-based fuel cladding tube surface scale on-line measurement device, which comprises an injection control module for injecting a radioactive 59Fe solution into a coolant and adjusting and controlling the 59Fe content by analyzing the Fe ion concentration; the test module is used for testing the surface of the fuel cladding based on the coolant injected with the radioactive 59Fe solution; and the measuring module is used for collecting the radioactive activity of 59Fe in scale generated on the surface of the fuel cladding after the test and speculating the scale mass surface density. According to the method, the content of the 59Fe in the coolant is controlled, and the radioactive activity of the 59Fe in the scale deposit on the surface of the fuel cladding is detected on line, so that the mass of the corresponding 59Fe can be accurately calculated, the scale deposit mass is speculated, the scale deposit information on the surface of a cladding pipe is obtained in real time, and the dynamic change condition of the scale deposit is reflected in time.

This invention discloses a method for producing radioactive isotopes in the core of an advanced high-temperature reactor using a spherical target. This invention overcomes the limitations of using neutron irradiation channels or fuel-related components of nuclear reactors, such as conditioning rods in heavy water reactors and combustible poison rods in pressurized water reactors, to produce radioactive isotopes. It sets a precedent for the mass production of radioactive isotopes using the core of a nuclear reactor, and has significant strategic implications for exploring high-value applications of commercial advanced high-temperature reactors to reduce operating costs and mass-produce radioactive isotopes, including the strategic isotope tritium.

The present invention relates to a remotely operated system (200) to deploy and recover materials (25) into and from a nuclear fusion device (100), for the purpose of exposing said materials (25) to neutron radiation, which will cause the generation of radioactive isotopes, comprising at least one loop made of pipes (14) with constant inner diameter, a plurality of capsules (23) with an outer diameter slightly smaller than the inner diameter of the at least one loop (14), wherein the capsules (23) are adapted to contain the material (25) to be irradiated by the neutron radiation, a propulsion system for circulating the capsules (23) through the at least one loop (14), a remotely operated capsule filling system (18) for filling said capsules (23) into the at least one loop (14), and a remotely operated capsule recovery system (19) for recovering said capsules (23) from the at least one loop (14).

The invention relates to the technical field of molecular biology, in particular to a group of SSR (Simple Sequence Repeat) molecular markers closely linked with a maize fusarium verticillium ear rot resistant QTL (Quantitative Trait Locus) and a detection method. As an SSR molecular marker, nucleic acid fragment SSR-51 and SSR-56 molecular markers are closely linked with the maize fusarium verticillium ear rot resistant gene, the recombination rate is low, the marker stability is high, and the primer can be used for effective detection, so that the molecular marker can be directly used for breeding links such as maize germplasm resource improvement, selfing line breeding and hybrid seed selection; according to the method, the disease-resistant genotype is identified through DNA detection in the corn seedling stage, and plant diseases do not need to be waited; the method has the advantages of high efficiency in detection, small quantity of required DNA samples, low requirement on DNA, simplicity in operation, high reliability, great allelic difference and no need of radioisotope.

The invention provides a vehicle power system suitable for lunar polar region exploration and a verification method, and relates to the technical field of deep space exploration, the system comprises a configurable energy module, a driving motor transmission mechanism, a power conversion management system, a thermal control subsystem and an autonomous driving controller; the energy module comprises a space fuel cell module, a wide-temperature lithium ion battery module, a solar cell panel module and a radioactive isotope battery module, and one or more of the modules can be selected to be combined according to task requirements. According to the invention, full-scene energy supply coverage of the monthly day, the monthly night and the permanent shadow area can be realized, uninterrupted propulsion of detection and transportation tasks is supported, and the task execution efficiency and the detection coverage range are greatly improved; meanwhile, it can be ensured that the driving power is accurately matched with the driving requirement of the complex terrain in the polar region of the moon, the driving power calculation deviation is effectively reduced, and the terrain passing capacity and operation stability of the vehicle are remarkably improved.

The invention discloses a high-pressure jet grouting pile diameter detection system based on an isotope thickness measurement principle and a use method of the high-pressure jet grouting pile diameter detection system. Comprising a drilling rod and a drilling table, the drilling rod is used for touching the side wall of the underground high-pressure jet grouting pile and measuring the pile diameter of the underground high-pressure jet grouting pile, and the drilling table is used for jacking the drilling rod into a soil layer. In order to realize pile diameter measurement, radioactive isotope solvent diffusion, radioactive intensity perception and diameter calibration back calculation methods are fused, and point-to-surface non-contact nondestructive diameter measurement is realized. And a strong spring, an inward pushing amount detection device and a simulated object hardness measurement method are adopted, so that whether a hard object at the front end of the drill rod is a pile body or not in the drilling process is effectively identified, and the information definition of the underground drilling condition is improved.

Process, Apparatus and System for the Production, Separation and Purification of Radioisotopes for medical, industrial, agricultural and energy applications.

This disclosure provides a method for measuring the release rate of a sample and an experimental cup. The method includes: placing a sample containing a specific element into the experimental cup and sealing it to constrain the position of the sample; irradiating the experimental cup containing the sample so that the specific element in the sample becomes radioactive by producing its own radioactive isotope; pouring a solution into the experimental cup and sealing it, immersing the sample in the solution to produce radioactive isotopes in the solution; measuring the content of radioactive isotopes in the solution at a set time; calculating the release rate of the radioactive isotopes of the sample based on the content and the inherent amount of the specific element in the sample, using the release rate to characterize the release of the radioactive sample into the human body during interventional therapy.

The present application belongs to the field of well logging operation, and particularly relates to a wellhead releasing device and a small-bore injection well logging method. In view of the problem that the conventional isotope tracing profile logging technology cannot meet the tracing profile logging requirements of the small-bore double-layer tubing injection well, a small-diameter multi-parameter logging instrument is optimized. Firstly, a radioactive isotope tracer wellhead releasing device is developed, which releases the isotope tracer into the well sections that are not communicated with each other by using the injection pressure difference between different injection sections and installing the wellhead releasing device on the wellhead Christmas tree. Secondly, the isotope tracer anti-dispersion method is studied, and the isotope tracer parameters are optimized, so as to improve the coagulation ability of the liquid isotope tracer in long-distance migration, thereby improving the logging interpretation accuracy. Thirdly, the releasing device and the isotope tracer preparation method are applied to improve the construction process, so as to complete the logging operation and meet the application and popularization.

The invention discloses a modified phenolic resin preparation method for radioactive waste oil solidification, relates to the technical field of nuclear radioactive waste treatment, and the preparation method includes modifying the phenolic resin obtained by base catalysis; preparing a lead-based metal organic framework; adding the prepared lead-based metal organic framework to dimethylformamide to obtain a lead-based metal organic framework suspension; weighing 1 to 5g of modified phenolic resin, adding it to 20-50 mL of methanol to obtain a modified phenolic resin solution; slowly pouring the lead-based metal organic framework suspension into the methanol solution of the modified phenolic resin, stirring the mixed solution with a magnetic stirrer for 30-60min, so that the lead-based metal organic framework is uniformly dispersed in the phenolic resin solution, and obtaining a lead-based metal organic framework-modified phenolic resin solution. The modified phenolic resin material of the present invention can not only solidify waste oil, but also simultaneously adsorb radioactive isotopes, and can effectively prevent leakage of radioactive waste oil.

The invention discloses a preparation system of a core-shell structure nano-micron radioactive logging tracer agent, which comprises a water phase preparation device, an oil phase preparation device, a balling device, a liquid circulating device and an organic coating device, and is characterized in that the water phase preparation device, the oil phase preparation device, the balling device, a circulating liquid storage tank and the organic coating device are connected through pipelines and valves; radioactive substances are prevented from leaking; according to the invention, radionuclide (such as iodine-131) is chemically embedded in the inner core of the tracer by adopting a core-shell structure design, so that the dissolution loss rate of radioactive isotopes is obviously reduced; the uniform preparation of the tracing microspheres is realized based on a micro-fluidic precise control technology; the physical embedding and chemical coating double barrier obviously improves the environmental safety of underground products.

A liquid target system (1) for producing radioactive isotopes, the liquid target system (1) comprising a boiling chamber (2) for containing a liquid and a base chemical by which a radioactive isotope can be produced by radiation, the boiling chamber (2) comprising a radiation window for effecting radiation on the liquid and the base chemical, causing the liquid to evaporate into vapor, wherein the liquid target system is configured such that the superheating of the liquid target (8) is controlled by the thermodynamics of the evaporation process, wherein the liquid is water or heavy water, and the base chemical is a salt having a positive enthalpy with respect to water.

The invention belongs to the technical field of medical radioactive isotopes, and particularly relates to an irradiation-resistant separation material for thorium-barium separation and a preparation method of the irradiation-resistant separation material. The preparation method comprises the following steps: preparing an active material; preparing a polyacrylonitrile matrix; preparing a composite material precursor solution; and molding the composite material. The prepared separation material has good thorium-barium separation performance, can tolerate irradiation with an absorbed dose of 300 kGy, and can be used for preparing an irradiation-resistant 228Th-224Ra generator.

The embodiment of the present application provides an isotope battery, comprising: a shell; an isotope light source arranged in the shell, the isotope light source is used for radiating photons outward, the isotope light source comprises a radioactive isotope film, wherein the photons are emitted outward from the circumferential side of the isotope light source, and the circumferential side is substantially perpendicular to the radioactive isotope film; and at least one photoelectric conversion device arranged in the shell, the at least one photoelectric conversion device faces the circumferential side of the isotope light source and is used for receiving the photons to convert into electric energy. Since the photons are emitted outward from the side of the isotope light source which is substantially perpendicular to the radioactive isotope film, and meanwhile each photoelectric conversion device faces the side of the radioactive isotope film, on the one hand, the photoelectric conversion device can receive a large number of photons, and on the other hand, the number of beta particles generated by the radioactive isotope decay entering the photoelectric conversion device can be greatly reduced, so that the photoelectric conversion body can be prevented from causing a significant irradiation dose.

The embodiment of the invention relates to the field of radioactive pollution liquid treatment, in particular to a radioactive waste liquid treatment device and method. In the waste liquid treatment device, the treatment module needs to contain a large amount of radioactive waste liquid in the operation process and bears a large weight, and the supporting module is arranged to support the treatment module, so that the operation of the treatment module is more stable, and the radioactive waste liquid is prevented from spilling outwards; meanwhile, the supporting module is detachable, so that the processing module can be conveniently separated from the supporting module, the processing module can be conveniently checked and maintained, and the radiation dose borne by an operator is reduced; the treatment module is arranged to be capable of containing a large amount of radioactive waste liquid, the radioactive waste liquid treatment efficiency can be improved, meanwhile, the maintenance or replacement frequency of the treatment module is reduced, and the yield of radioactive secondary waste is reduced. In the radioactive waste liquid treatment method, by monitoring the content of radioactive isotopes in the treated radioactive waste liquid, it is ensured that the radioactive waste liquid is safely discharged after being treated to reach the qualified standard, and harm to the environment is avoided.

The invention discloses a beam scanning control method for high-power radioactive isotope production, relates to the technical field of magnetic deflection, and adopts a pair of alternating current scanning magnets which are perpendicular to each other to carry out two-dimensional dynamic scanning on beams, and realizes self-adaptive control through closed-loop feedback. Comprising the following steps: firstly, initializing set scanning parameters and control targets including uniformity; then multi-source data such as the total intensity, the central position and the two-dimensional intensity distribution of the beam current are synchronously collected; calculating a position deviation and uniformity index based on this; and dynamically adjusting the amplitude, frequency or waveform of the scanning signal according to the deviation and the difference between the uniformity and the target so as to optimize the uniformity of the target surface. And finally, through continuously iterative closed-loop feedback, the beam uniformity is stabilized in a preset target range. The distribution of the beam on the target surface is actively shaped and stabilized within the preset uniformity range, so that local overheating is avoided, and the power bearing capacity and the automation level of isotope production are improved.

This invention discloses a method and apparatus for analyzing seepage channel evolution based on natural radioactive isotopes, comprising: establishing a single-event response model based on the physical process of seepage channel evolution triggering abnormal nuclide release; modeling the macroscopically observed nuclide concentration time series signal as a weighted superposition of multiple single-event response models to construct a physics-driven forward model; using an iterative encryption optimization algorithm to invert and obtain the optimal number of seepage channel evolution events and parameter set, and substituting them into the physics-driven forward model to achieve high-fidelity reconstruction of the nuclide signal; and extracting quantitative evaluation indicators of seepage channel evolution based on the optimal parameter set obtained from the inversion. This invention realizes a paradigm shift from "observed signal spectrum" to "seepage channel evolution source spectrum," and the obtained parameters provide highly reliable input for various monitoring and analysis systems, significantly improving the reliability and automation level of monitoring and analysis mechanisms, and providing precise technical support for related application scenarios.

A composition of microparticles includes a non-radioactive and a radioactive isotope, and an injection vehicle, for use in the intratumoral treatment of cancer, by combined antitumoral effect of radioactivity and intratumoral microparticle deposition. The antitumoral effect provided by the cytotoxicity of radioactivity is enhanced by a modulation of the tumoral immune response induced by microparticle deposition inside the tumor, thereby decreasing the dose of radioactivity required to treat solid tumors. A method of treating solid tumors using a sub-optimal tumor-volume coverage dose of radioactivity combined with intratumoral microparticle deposition as a mean of tumor control is also disclosed.

A method for purification of a target material for re-use in the production of radio-isotopes is disclosed, and includes obtaining a solution of irradiated target material, comprising Ra-226 and optionally Ra-225 and Ac-225, and subsequently adding an acid, being HNO3, in a predetermined quantity and providing conditions for quantitatively dissolving the target material and avoiding co-precipitation of the optionally present radio-isotopes. The method includes selectively removing H2O from the solution by distillation, leaving the acid predominantly inside the solution thereby allowing the target material to precipitate while the acid concentration in the solution increases and thereby reducing or avoiding co-precipitation of the optionally present radio-isotopes and impurities. After removal of the excess H2O, the method comprises lowering the temperature of the solution to maximize the precipitation of the target material and reduce the solubility of the target material in the remaining liquid.

To provide a radioactive isotope production apparatus that can stably produce radioactive isotopes while miniaturizing superconducting accelerators. [Solution] The above problem can be solved by a radioactive isotope manufacturing apparatus comprising an electron gun that outputs an electron beam E, an accelerator that accelerates the electron beam E by superconductivity, a cooling unit that cools the accelerator, a manufacturing unit that receives the electron beam E accelerated by the accelerator to produce a radioactive isotope, and a high-frequency source R that inputs high frequency to the accelerator, wherein the accelerator is equipped with a high-frequency cavity that receives high frequency from the high-frequency source to provide acceleration energy to the electron beam, and the cooling unit is equipped with a conduction cooling attachment that conductionally cools the entire cavity body 21 between an expander and the cavity body 21 of the high-frequency cavity.

The invention relates to a continuous method for separating strontium cations from a liquid medium containing at least one strontium cation, in particular at least one radioisotope of strontium, for example a cation of 90Sr, in which method the liquid medium is brought into contact with a solid mesoporous material, a solid mesoporous material includes an inorganic matrix made of a mesoporous geopolymer having open mesopores and microparticles of at least one solid inorganic exchanger compound selective for strontium cations and different from the geopolymer, the geopolymer having a single pore size, the particles are distributed in open mesopores of the inorganic matrix and can be in contact with strontium cations contained in the liquid medium; the solid mesoporous material is in the form of non-powdered particles forming a fixed bed, in particular a column filler.

The present invention provides a target irradiation system that allows the target to be removed from the irradiation device and the radioactive isotope to be quickly dissolved in a dissolution device, and a method for recovering radioactive isotopes from a solid target. [Solution] The transport device 22 transports the solid target 10 from the target irradiation device 20, where the charged particle beam B is irradiated onto the solid target 10, to the dissolution device 21, which recovers the radioactive isotopes. Here, the target irradiation device 20 and the dissolution device 21 are located in a cyclotron chamber 152 provided in the building 150. Therefore, both the process of irradiating the solid target 10 with a charged particle beam and the process of recovering the radioactive isotopes by dissolution are performed in the cyclotron chamber 152. Thus, the solid target 10 can be removed from the target irradiation device 20 and the radioactive isotopes can be quickly dissolved in the dissolution device 21.

The utility model provides dosing equipment capable of automatically dropwise adding nuclide solution, which belongs to the technical field of medical instruments and comprises a case, a platform and a planar motion mechanism are mounted in the case, and a planar area where the planar motion mechanism is located corresponds to a planar area where the platform is located up and down; the automatic medicine feeding module is connected with the planar motion mechanism, the planar motion mechanism is arranged to enable the automatic medicine feeding module to move to the position over any position of the platform, and the automatic medicine feeding module is arranged to be of a structure capable of dropwise adding medicine liquid; the automatic dosing device has the advantages that the automatic dosing device used in the nuclide applicator preparation process is provided, the planar motion mechanism is matched with the automatic dosing module, nuclide solution can be dropwise added to the filter paper of the platform, the operation step of manual dosing is omitted, workers are prevented from making direct contact with radioactive isotopes, and the working efficiency is improved. And the workload of nuclide applicator preparation is greatly reduced.

The invention provides a radioactive contamination detection training dummy, and relates to the field of training dummy. The radioactive contamination detection training simulation human comprises a simulation head, a body simulation assembly, two simulation arms, a simulation body and two simulation legs, the body simulation assembly comprises a connecting block, the simulation head is inserted into the upper end of the connecting block, a shoulder cover is fixedly arranged at the lower end of the connecting block, an inner box is fixedly arranged at the midpoint of the lower end face of the shoulder cover, and the lower end face of the inner box is provided with an outer box. A plurality of first radioisotope simulation capsule array blocks are fixedly arranged on the outer wall of the inner box, the first radioisotope simulation capsule array blocks are vertically arranged at equal intervals, the inner box is embedded into the simulation trunk, and a connecting block penetrates through the upper end of the simulation trunk; each of the two simulation arms comprises a first arm shell, a second arm shell and a mounting plate. The anthropomorphic dummy can realize comprehensive radioactive contamination simulation so as to facilitate rapid detection and identification during training, and is more convenient to operate.

The present invention provides a radioactive isotope carbon-14 labeled methoprene and its preparation method, including the steps: S1: Prepare [cyano-<supgt;14< / supgt;C](R)-7-methoxy-3,7-dimethyloctanenitrile; S2: Prepare [aldehyde group-<supgt;14< / supgt;C]citronellal; S3: Prepare carbon-14 labeled methoprene. It fills the blank in the related field of radioactive isotope carbon-14 labeled methoprene, enabling it to provide accurate and reliable tracer information when studying the behavior of methoprene in organisms and the environment, and providing a powerful tool for in-depth exploration of the metabolic process, environmental behavior, pharmacokinetics, etc. of methoprene, which helps to promote the development of related field research, such as optimizing the use strategy of methoprene in agricultural pest control, etc.

The invention discloses a method for removing natural radioactive isotope 138La in lanthanum oxide powder by using neutron irradiation. The method comprises the following steps: firstly, according to a neutron capture cross section curve of 138La in an ENDF / B-VIII.1 nuclear evaluation database, determining the optimal neutron energy as 3 eV; lanthanum oxide powder is packaged in a high-purity quartz ampoule which is placed in a neutron irradiation channel of a reactor. Most neutrons are moderated into epithermal neutrons with the energy of 3 eV by a heavy water layer of the reactor, and then the epithermal neutrons are emitted into lanthanum oxide powder. The neutron capture efficiency of the 138La in the irradiation process is obtained according to a Monte Carlo simulation method, the irradiation time required for completely converting the 138La into the 139La can be calculated by combining neutron flux data of a reactor, the mass of lanthanum oxide powder and the abundance ratio of the 138La, and the yield of the by-product 140Ce is evaluated. After irradiation is finished, standing and cooling are conducted for a period of time, the lanthanum oxide powder is placed in a low-background lead chamber, the residual radioactivity level of the lanthanum oxide powder is evaluated through a high-purity germanium detector, and the removal effect of 138La in the lanthanum oxide powder can be determined.

The present invention provides a radioactive isotope production system and a radioactive isotope production method that can be miniaturized. [Solution] According to this radioactive isotope production system 100, the target 10 after irradiation with charged particle beam B is made smaller than it was during irradiation, and the radioactive isotope is recovered. Figure 6(b) shows what happens when the target 10 after irradiation with charged particle beam B is placed in the purification apparatus 103 at its original size. As shown in Figure 6(b), because the size of the target 10 is large, the internal space 31 needs to be enlarged, and as a result, the entire purification apparatus 103 must be enlarged. In contrast, by making the target 10 smaller after irradiation, a smaller purification apparatus 103 can be used, as shown in Figure 6(a). Thus, the system can be miniaturized.

The invention discloses a fission fragment collection and activity separation device and a collection and separation method, and relates to the technical field of radioactive isotope detection. The linear driving device is mounted at the upper end of the supporting bottom plate; the drawstring winding device is installed on the linear driving device, the drawstring winding device is connected with a drawstring body, and the linear driving device can drive the drawstring winding device and the drawstring body to move towards the detection device; the vacuum isolation chamber is provided with a first connector, a second connector, a third connector and a fourth connector, the second connector is connected with an inflation device, the third connector is connected with a vacuum device, and when the interior of the vacuum isolation chamber is in a negative pressure state, the fourth connector is used for adsorbing the drawstring body; and one end of the vacuum chamber is connected with the first interface, and the other end of the vacuum chamber is connected with the ion accelerator. The radioactive isotope activity separation device can be used for activity separation of radioactive isotopes, and is simple in structure and low in manufacturing cost.

This invention discloses a purification apparatus and method for iodine-131 produced by a nuclear reactor using uranyl nitrate aqueous solution as fuel, relating to the field of radioactive isotope production technology. The apparatus includes a carrier gas cylinder, an evaporator, a waste liquid tank, a primary absorption tank, a secondary absorption tank, a tertiary absorption tank, and a product tank. The carrier gas cylinder is connected to the evaporator via an inlet pipe. A liquid inlet is located at the top of the evaporator. An outlet pipe is connected to the top of the evaporator, connecting to the primary absorption tank. The primary absorption tank is connected to the secondary absorption tank via a pipe, and the secondary absorption tank is connected to the tertiary absorption tank via a pipe. Discharge pipes are connected to the bottom of the primary, secondary, and tertiary absorption tanks, and these pipes are all connected to the product tank. The bottom of the evaporator is connected to the waste liquid tank via a drain pipe. This apparatus and method achieve high product recovery and high product purity after iodine-131 purification. 131 The sodium hydroxide solution product meets the requirements of medical technical specifications.