37 results about "Radiogenic Isotopes" patented technology

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.

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 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 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.

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 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 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.

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.

The invention discloses a method for intelligently detecting the blocking position of a coal mine filling pipeline by using radioactive isotopes, and belongs to the technical field of coal mine filling pipeline filling. The technical problems that in the prior art, a detection method is low in efficiency and poor in economical efficiency are solved. A required system comprises a pipeline pressure monitoring system, a data processing and feedback system and a hierarchical linkage control system, the pipeline pressure monitoring system comprises a pipeline main body and a scintillation liquid coating, and the pipeline main body comprises a flexible inner pipe, a particle escape space area and a rigid outer pipe from inside to outside; and the data processing and feedback system is used for transmitting, storing, analyzing and processing data acquired by the multichannel analyzer, the temperature sensor and the flow sensor. According to the method, the blockage position of the coal mine filling pipeline can be accurately judged, meanwhile, a grading early warning feedback system is established, a linkage control strategy is appointed, reliable data are provided for underground workers and ground dispatching personnel in time, and safety guarantee is provided for blockage prevention and explosion prevention of the filling pipeline.

The invention relates to the field of groundwater replenishment mode research, in particular to a method for identifying a groundwater replenishment mode in a thick vadose zone area through combination of multiple tracers. The method solves the problem that the groundwater supply process in a thick aeration zone-aquifer system is difficult to find. The method comprises the following specific steps: 1, observing the shape of tracers (Cl <->, NO3 <-> and 3H) in a farmland / grassland soil profile; 2, analyzing the change of underground water tracers (Cl <->, NO3 <->, delta D, delta 18O and the like) along with time and the response of the underground water tracers to rainfall; 3, determining the tritium content and 14C apparent age of underground water; and 4, comparing the similarity of the composition of rainfall, soil water and groundwater isotopes (deltaD, delta18O), and evaluating the evaporation effect. According to the method, a plurality of chemical tracers, stable isotope and radioactive isotope fingerprint technologies are combined, the groundwater supply mode is evaluated at the same time from the aspects of the aeration zone and the saturation zone, the accuracy of the identification result is verified through multiple technical means, and a comprehensive method framework is provided for solving the groundwater supply mechanism in the thick aeration zone area.

The present invention relates to a method for forming an optical waveguide sensor for detecting ions containing radioactive isotopes in an aqueous solution. The method comprises treating a substrate surface by cleaning the substrate surface with one or more solvents to enable coating with a crosslinking agent, the substrate being selected from silica or silicon substrate, coating the treated substrate surface with the crosslinking agent selected from carboxylic acid functional group containing organic molecules to form a crosslinked substrate surface, coating the crosslinked substrate surface with a scintillating agent, and coating the substrate surface with a ligand capable of reacting with a radioactive isotope in an aqueous solution to form a functionalized substrate surface. The present invention also relates to the optical waveguide sensor for detecting radioactive isotopes fabricated with the method of the present invention.

The invention discloses a high-pollution-resistance radioactive isotope tracing microsphere and a preparation method thereof. The tracing microsphere is composed of a zeolite / polystyrene composite carrier core, a polyvinyl alcohol curing radioactive source layer, a chitosan hydrophilic pollution-resistance layer and an inorganic-organic composite mineralization shell in sequence. The preparation method comprises the following steps: preparing an iodine-131-containing polyvinyl alcohol aqueous solution and a chitosan acid solution; the preparation method comprises the following steps: mixing zeolite powder and polystyrene powder, and spraying a radioactive polyvinyl alcohol solution in a rolling device to obtain a radioactive isotope-containing microsphere core; spraying a chitosan solution on the surface of the microsphere core by adopting a fluidized coating process, and neutralizing and curing by ammonia water to form a chitosan layer; then the microspheres are placed in a mineralization system containing calcium chloride, sodium carbonate and polyacrylic acid for a reaction, and a calcium-containing inorganic-organic composite mineralization shell layer attached to the outer side is constructed. The adhesion and retention trend of the tracing microsphere in a shaft environment is remarkably reduced, radioactive contamination can be effectively relieved, and the signal-to-noise ratio and profile interpretation precision of tracing logging are improved.

The utility model relates to the technical field of deep-sea unmanned detection, in particular to a long-endurance deep-sea unmanned detection device which comprises a detector body and a propeller, the detector body is of a streamline structure and comprises a main shell and a tail shell, a controller is arranged in the main shell, the tail shell comprises a front cavity and a rear cavity, and the propeller is arranged at the tail end of the outer side of the rear cavity. A heat source and a thermoelectric conversion module are arranged in the front cavity, a storage module is arranged in the rear cavity, the controller and the thermoelectric conversion module are electrically connected with the storage module, the cold end of the thermoelectric conversion module covers the circumferential inner wall of the front cavity in an attached mode, and the hot end of the thermoelectric conversion module covers the circumferential outer side of the heat source in an attached mode. According to the utility model, direct conversion from heat energy to electric energy is realized through Seebeck effect by utilizing a stable heat source generated by decay of radioactive isotopes with extremely high energy density and utilizing a low-temperature condition of a deep sea environment, so that the cruising ability is improved to the greatest extent; and long-term and large-scale continuous scientific observation and resource exploration can be carried out on deep-sea plains and sea ditch areas.

This invention relates to a method for the large-scale preparation of highly stable cesium removal adsorbents, as well as their products and applications. Specifically, this invention relates to a particulate inorganic oxide or activated carbon supported transition metal-stabilized ferrocyanide adsorbent, comprising: a particulate inorganic oxide support or a particulate activated carbon support; a transition metal-stabilized ferrocyanide layer coating the inorganic oxide or activated carbon support; and a polymer material layer coating the transition metal-stabilized ferrocyanide layer. This adsorbent exhibits high crushing strength and low ion leaching rate. This invention also relates to a method for preparing this adsorbent and its applications in removing radioactive isotope Cs ions and stable isotope Cs ions, as well as in removing radioactive isotope Rb ions and stable isotope Rb ions.

The invention discloses tungsten alloy protection equipment and application thereof, and solves the problems that radioactive isotope drugs possibly volatilize after being stored, and workers and the environment are harmed when the radioactive isotope drugs are taken again, the tungsten alloy protection equipment comprises a storage cylinder assembly, and the storage cylinder assembly is installed on the inner side of an outer frame; a medicine storage assembly is arranged at the top end of the storage cylinder assembly, the storage cylinder assembly comprises an outer cylinder, an inner cylinder is installed on the inner side of the outer cylinder, a negative pressure cavity is formed between the outer cylinder and the inner cylinder, a fan is installed in the inner cylinder, an exhaust pipe is installed at the bottom end of one side of the inner cylinder, and a communication control unit is arranged on the inner cylinder. The communication control unit comprises first communication grooves symmetrically formed in the two sides of the inner barrel, and the first communication grooves are located above the draught fan. According to the radioactive isotope medicine taking device, in the working process, when the second communicating groove and the first communicating groove in the supporting sealing plate are staggered, radioactive isotope medicine volatile gas in the inner barrel can be exhausted through the fan, and the medicine taking safety is improved.

Described are techniques for distinguishing between biomethane and fossil methane using isotopic analysis. Examples include evaluating a methane source using radioisotope analysis stable isotope analysis. In some cases, radioisotope analysis is used for purposes of calibrating a stable isotope analysis technique or for verifying precision or reliability of a stable isotope analysis result.

The application designs a method for producing Mo isotopes by using a target and a shell in a strong current proton cyclotron 68 Ge- 88 Zr- 93m The method comprises the following steps: selecting multiple target nuclides capable of fully utilizing the energy interval of the accelerator; producing two target nuclides corresponding to the energy interval of each nuclide, wherein the reaction cross-section peak region of one target nuclide corresponds to the reaction cross-section valley region of the other target nuclide; selecting the target and the shell for producing different target nuclides in different nuclide production energy intervals, and in the same nuclide production energy region, the reaction cross-section peak region of the target for producing the target nuclide corresponds to the reaction cross-section valley region of the shell for producing the target nuclide; or in the same nuclide production energy region, the reaction cross-section peak region of the shell for producing the target nuclide corresponds to the reaction cross-section valley region of the target for producing the target nuclide. The capsule cascade target maximizes the production of radioactive isotopes, reduces the irradiation cost of the accelerator operation, and improves the production efficiency of isotopes.

A method for producing a radionuclide comprises irradiating a target material with a linear accelerator to produce a radionuclide, dissolving the irradiated target material comprising the radionuclide, and separating the radionuclide from the irradiated target material. The irradiated target material may be dissolved in an acidic solution comprising one or more mineral acids. The target material may include a tungsten target material, such as a natural tungsten target material comprising one or more of 180W, 182W, 183W, 184W, and 186W or a tungsten target material exhibiting an elemental purity of about 99.95%. Additional methods for producing tantalum radioactive isotopes are disclosed.

A method is provided for separating lead radioactive isotopes from a mixture containing lead radioactive isotopes and radium or thorium radioactive isotopes, along with a system comprising multiple chromatography columns. The system may comprise a first cartridge having a lead complex-forming medium that preferentially binds to lead radioactive isotopes rather than radium or thorium radioactive isotopes, and a second cartridge having a weak cation exchange medium, wherein the pH of the loading solution used to load the second cartridge is pH 2L Furthermore, the pH of the eluent used to elute the lead radioactive isotope from the second cartridge is pH 2E And, 2L pH 2E Higher. The system may further include third and fourth cartridges having chromatographic media for extracting and purifying the lead radioactive isotopes so as to provide a purified lead radioactive isotope solution that can be used for medical and other applications, such as labeling radiopharmaceutical compounds.

The invention discloses an underwater out-of-ray detection device which comprises an equipment rack suitable for underwater use, the equipment rack is provided with a two-half mechanism capable of being opened and closed through a shaft, the two-half mechanism is divided into a fixed part and a rotatable part, one half of the rotatable part is provided with an accelerator pressure-resistant cabin, the other half of the rotatable part is provided with an accelerator pressure-resistant cabin, and the accelerator pressure-resistant cabin is provided with an accelerator pressure-resistant cabin. An accelerator of which the X-ray energy is not lower than 4MeV is arranged in the pressure-resistant cabin; a detector pressure-resistant cabin is arranged on the other half opposite to the accelerator pressure-resistant cabin, and an array detector is arranged in the detector pressure-resistant cabin and is used for receiving X-rays. The underwater ray external detection device adopts the high-energy X-ray accelerator as a ray source, and compared with traditional radioactive isotopes, the underwater ray external detection device has higher penetrating power and can effectively penetrate through a seabed oil pipeline with a large pipe diameter, a thick wall or a composite structure, and the detection application range is remarkably widened. The device can perform external clamping type scanning on the premise of not disassembling the pipeline, is suitable for real-time health monitoring of the in-service pipeline, and reduces production halt loss.