1353 results about "Nuclear chemistry" patented technology

The invention relates to the technical field of unmanned aerial vehicle-mounted nuclear radiation detection, and provides an unmanned aerial vehicle-mounted nuclear radiation detection method and system based on deep learning, and the method comprises the steps: collecting a gamma energy spectrum signal, and carrying out the digitization of the gamma energy spectrum signal, and obtaining original energy spectrum data; preprocessing the original energy spectrum data to obtain preprocessed energy spectrum data; constructing a nuclide identification model based on a deep learning network, and performing nuclide identification on the preprocessed energy spectrum data to obtain an original nuclide identification result; performing post-processing analysis and refinement on the original nuclide identification result to obtain a nuclide identification result; and fusing the nuclide identification result with the geographic position information to obtain a nuclear radiation pollution distribution diagram, and setting a multi-level early warning mechanism based on nuclide types and intensity. According to the invention, the precision of nuclide identification in a complex environment is improved, and high-sensitivity detection of various nuclides under the condition of low signal-to-noise ratio is realized.

The invention provides a microdosimetry-based evaluation method for a targeted alpha radionuclide treatment biological effective dose, and the method comprises the steps: carrying out the integration of a time activity curve of alpha radionuclide in an organ, obtaining the cumulative activity, and calculating the physical absorbed dose and dose rate of the organ through Monte Carlo simulation; based on micro-dose Monte Carlo simulation, constructing a micro-dose spectrum of the alpha radionuclide to obtain saturation correction dose average linear energy for representing radiation quality; obtaining biological effect parameters of the alpha radionuclide by fitting saturation correction dose average line energy and cell experiment data by using a micro-dose kinetic model; and evaluating the biological effective dose of the target organ in combination with the physical absorbed dose, the dose rate and the biological effect parameter. According to the method, the problem that a biological effective dose evaluation method is lacked in dose evaluation of targeted alpha radionuclide treatment is solved.

The invention discloses a method and tool for manufacturing a cold shield of a nuclear fusion device, and relates to the technical field of metal plate machining. The manufacturing method of the cold shield of the nuclear fusion device comprises the following steps: providing a sub-panel, a flange and a pipe fitting; the multiple sub-panels are welded, and a first middleware is obtained; welding the edge of the first middleware and the turnup to obtain a second middleware; after the pipe fitting is welded to the surface of the second middleware, a third middleware is obtained; and the third middleware is shaped. According to the method, the third middleware is shaped, that is, the third middleware is shaped after all welding procedures are completed, so that the third middleware has relatively small profile tolerance, the profile tolerance of the cold shield meets the design requirement, the assembly difficulty of the cold shield is reduced, and the risk of failure of the cold shield is reduced.

The invention provides a samarium / europium / gadolinium-containing zirconium hydride block as well as a preparation method and application thereof, and relates to the technical field of radiation shielding materials. The zirconium hydride block containing samarium / europium / gadolinium comprises the following elements in percentage by mass: 95% < = Zr < = 99.5%, 0% < = Gd < = 5%, 0% < = Sm < = 5%, 0% < = Eu < = 5% and 0% lt. Gd + Sm + Eu < = 5%. The preparation method comprises the following steps: respectively hydrogenating sponge zirconium, metal gadolinium, metal europium and metal samarium to respectively obtain corresponding hydride powder; weighing zirconium hydride powder, gadolinium hydride powder, europium hydride powder and samarium hydride powder according to a required proportion, and uniformly mixing under a protective atmosphere; and carrying out pressure sintering on the mixed powder, and carrying out secondary hydrogenation to obtain the zirconium hydride block containing samarium / europium / gadolinium. According to the invention, the absorption of the material to low-energy-segment neutrons can be obviously improved; and the preparation of the zirconium hydride block containing samarium / europium / gadolinium and the accurate regulation and control of doped elements are realized.

The invention relates to the technical field of safety monitoring of a nuclear reactor, and particularly discloses a multi-region pressure overrun leakage monitoring method for a reactor pressure vessel. The method comprises the steps of multi-region pressure data acquisition, real-time pressure field model construction, dynamic pressure field baseline modeling, pressure overrun anomaly detection, leakage source accurate positioning and evaluation based on spatial gradient analysis, topological structure mapping and multi-sensor data fusion, and graded early warning and response. By the adoption of the technical scheme, real-time and fine monitoring of pressure distribution in the reactor pressure vessel can be achieved, the rapid and accurate judgment and positioning capacity of leakage events is improved, the operation safety and reliability of nuclear power facilities are enhanced, and the reliability of the nuclear power facilities is improved. The defects of independent monitoring, local accurate positioning and complex working condition adaptability of multi-region pressure over-limit leakage in the prior art are overcome.

The present invention discloses a medical microsphere and its preparation method and application. The medical microsphere includes phenolic resin microspheres and radioactive metal elements loaded on the phenolic resin microspheres; the average particle size of the phenolic resin microspheres is 1 to 150 μm. The medical microsphere in the present invention can not only achieve local cell killing in the blood vessels of a specific part, but also effectively avoid the occurrence of fragmentation; further, the medical microsphere has a good loading rate and an extremely low exudation loss rate, which can meet the loading and safety requirements of radioactive elements; in addition, the preparation method of the medical microsphere is simple.

The invention discloses a metal polyphenol network modified drug-loaded radioactive microsphere as well as a preparation method and application thereof, radionuclides are labeled on different microspheres by a precipitation method or an adsorption method, and the metal polyphenol network is modified on the surface of the radioactive microsphere to improve the nuclide labeling stability and the synchronous drug loading capability of the radioactive microsphere. Subsequently, medicine molecules can be adsorbed to the modified radioactive microspheres to obtain the metal polyphenol network modified medicine-carrying radioactive microspheres. The metal polyphenol network modified drug-loaded radioactive microspheres prepared by the invention can solve the problems of radionuclide non-target shedding and DNA damage repair caused by nuclear drugs, avoid secondary drug administration, ensure that drugs directly and accurately reach tumor targets, and improve the drug delivery efficiency. And the selective internal irradiation therapy based on radioactive microsphere mediation is further promoted to play a more effective tumor treatment effect.

The present invention relates to a lead plate installation construction method for a radiation protection project in a radiological medical room, which mainly includes the following steps: S1. After the main structure of the radiological medical room is completed and passed the acceptance, the radiation protection project and the secondary decoration project are started; S2. The technical scheme of the radiation protection project is determined; S3. The radiation protection project is carried out on the ground; S4. The radiation protection project is carried out on the wall; S5. The radiation protection project is carried out on the ceiling; S6. The fine decoration construction is carried out according to the fine decoration construction drawing. This construction method solves the key link of the radiation protection project - the problem of lead plate installation, and can ensure that the lead plate fits the medical room without dead angles, provides all-round protection for the radiological medical room, and effectively prevents the leakage of harmful rays that endangers personal safety; at the same time, it takes into account the fine decoration construction requirements of the radiological medical room, and ensures a close connection between the radiation protection project and the fine decoration project.

The invention relates to the technical field of nuclear reactor and electrical equipment fault diagnosis, in particular to a nuclear reactor electrical penetration assembly fault mode diagnosis method and system, and provides a new nuclear reactor electrical penetration assembly fault mode diagnosis method. The method comprises the following steps of: designing a self-adaptive threshold value of each dimension of the electrical penetration device and an operation state reliability evaluation weight algorithm according to the characteristics of an electrical operation fault of the electrical penetration device and the characteristics of a sealed operation fault of the electrical penetration device, comprehensively performing operation diagnosis of the new mass reactor electrical penetration device, and comprehensively performing multi-dimensional comprehensive fault characteristic variables including the relation of original fault characteristics and the relation of the new mass reactor electrical penetration device. And meanwhile, the original fault features are utilized more sufficiently, so that the multi-dimensional operation diagnosis result of the electrical penetration device is more accurate, and the actual application requirements of a new mass heap site are fully met.

The invention provides an energy gradient utilization steam Rankine cycle power generation system and method for nuclear fusion, and belongs to the field of nuclear fusion energy conversion and utilization. Different temperature heat of a cladding, a divertor and a vacuum chamber is guided into a high-temperature independent heat storage loop, a medium-temperature independent heat storage loop and a low-temperature independent heat storage loop respectively, an operation section stores heat, and a pause section releases heat; feed water is heated step by step through a multi-stage preheater, an evaporator and a superheater according to the sequence of low temperature, medium temperature and high temperature, and superheated steam of 550 DEG C is formed to continuously drive a turbine to generate power. Decoupling of intermittent output of the fusion reactor and continuous operation of the power generation system is achieved, steam extraction of a steam turbine is omitted, the structure is simplified, and the energy utilization rate and the circulation efficiency are improved.

The present application pertains to processes for making calcium oxide and / or sulfuric acid from calcium sulfate. In some embodiments the processes comprise reacting a component comprising calcium sulfate with a second component comprising magnesium sulfite under conditions to form a solid comprising calcium sulfite and a solution comprising magnesium sulfate. Next, at least a portion of the solid comprising calcium sulfite is decomposed to form a second solid comprising calcium oxide, or calcium hydroxide, or cement, or clinker, or any combination thereof.

The invention provides an integrated mounting system and method for a high-temperature gas cooled reactor core supporting structure, and relates to the technical field of nuclear power construction, the integrated mounting system for the high-temperature gas cooled reactor core supporting structure comprises a pre-assembly plant, and a bridge crane is arranged in the pre-assembly plant; the first operation platform is provided with pre-assembly cabins arranged in multiple rows and multiple columns, each pre-assembly cabin is correspondingly provided with two cantilever cranes, and the cantilever cranes are used for reshipment, namely installation, of equipment in the pre-assembly cabins. The integrated mounting system for the high-temperature gas cooled reactor core supporting structure solves the problem that the reactor core supporting structure is lack of an integrated pre-assembly environment outside a nuclear island plant, and provides guarantee for smoothly realizing integrated pre-assembly of the reactor core supporting structure outside the nuclear island plant; the construction difficulty is correspondingly reduced, the construction operation environment is improved, and the construction level of nuclear power engineering in China and the economical efficiency of high-temperature gas cooled reactor nuclear power are improved.

The invention belongs to the technical field of biological medicines, and particularly relates to an iron-based nano material, a preparation method and application of the iron-based nano material in preparation of medicines for treating breast cancer. The iron-based nano material is formed by loading a ferroptosis inducer on a nano carrier; the nano carrier is an iron-based metal organic framework material Fe-MOF (Metal Organic Framework). A product FEH for treating breast cancer is obtained based on coupling of the iron-based nano-material provided by the invention with a targeted drug such as trastuzumab. The FEH provides a new method for developing a nano platform with an antibody function, and realizes a treatment strategy of trastuzumab and ferroptosis combined anti-tumor. As a safe and effective tumor treatment strategy, the EFH has huge clinical transformation potential.

The invention relates to the technical field of pipeline decontamination, in particular to an online pipeline ultrasonic decontamination device and method suitable for various pipe diameters, and the online pipeline ultrasonic decontamination device comprises a numerical control generator, a transducer, an amplitude-change pole, an adaptive clamp, an online monitoring device and other key components. And through the designed adaptive clamp, the device can act on pipelines with various pipe diameters and can move along the pipelines, and the decontamination requirements in different scenes are met. The online ultrasonic decontamination device is suitable for maintenance and cleaning work of pipelines with different pipe diameters in nuclear power facilities, and has important significance in improving the safety of the nuclear facilities and guaranteeing radiation protection for operators. The problem that an ultrasonic device is poor in applicability is effectively solved, meanwhile, the flexibility of the device is guaranteed, effective online decontamination of pipelines with various pipe diameters can be achieved through a single set of device, the decontamination cost of radioactive contamination of nuclear facility pipelines is effectively reduced, online efficient decontamination of radioactive contamination deposited in the pipelines is achieved, and the service life of the pipelines is prolonged. The safe and stable operation of the reactor is ensured, and the radiation risk of operators is reduced.

The application proposes a nuclear emergency training platform, and the platform comprises a nuclear emergency simulation system which is used for simulating the scene of a nuclear power plant accident, generating a training result according to the emergency operation data of each trainee, and transmitting the training result to a nuclear emergency command system; the nuclear emergency command system is used for acquiring a guidance suggestion corresponding to the training result, generating a training guidance report according to the guidance suggestion and the training result, and sending the training guidance report to the terminal equipment of the trainees; and the terminal equipment of the trainees is used for receiving and displaying the training guidance report. According to the scheme, the nuclear emergency simulation system, the nuclear emergency command system and the terminal equipment of the trainees are connected, so that the emergency command system can give more authoritative guidance suggestions to the training conditions of the trainees in time, and meanwhile, the trainees can obtain training guidance reports in time to correct the emergency operation behaviors of the trainees in time; therefore, the emergency processing capability of trainees can be greatly improved.

The invention belongs to the technical field of nuclear power station safety, and particularly relates to a method and system for comprehensively carrying out nuclear power station risk assessment. Comprising a data acquisition module, a risk assessment module, an intelligent early warning module and an emergency response module. The data acquisition module acquires data influencing the safety risk of the nuclear power station, including nuclear power station equipment operation data, radiation and environment data, personnel data and external risk data; the risk assessment module calculates a risk value through a nuclear power station risk assessment model; the intelligent early warning module performs early warning grade division and displays early warning information on a monitoring interface; and the emergency response module automatically adjusts an emergency response plan and optimizes resource configuration according to the early warning level. The system has the beneficial effects that the data acquisition and integration module acquires nuclear power station equipment operation data, radiation and environment data, personnel data and external risk data, so that factors causing potential risks of the nuclear power station are obtained, and data support is provided for comprehensive risk assessment of the nuclear power station.

The invention discloses a nuclear power plant reactor core fuel assembly uranium contamination fission product calculation method and system, and the method comprises the following steps: monitoring the characteristic nuclide of a loop coolant of a reactor core fuel assembly in real time, and judging whether the surface of the reactor core fuel assembly has uranium contamination; if the uranium contamination exists, calculating the uranium contamination amount of the uranium contamination distributed in the primary loop coolant on the surface of the reactor core fuel assembly; and calculating uranium contamination fission product distribution of the reactor core fuel assembly according to the uranium contamination amount. According to the method, the uranium contamination fission product distribution in the primary loop coolant is collected, so that the risk of erroneous judgment of the damage of the reactor core fuel assembly caused by uranium contamination can be remarkably reduced.

The invention belongs to the field of graphite materials, and particularly relates to nuclear-grade natural graphite, preparation of the nuclear-grade natural graphite and application of the nuclear-grade natural graphite to preparation of high-temperature gas cooled reactor fuel spherulis.The preparation method comprises the steps that a natural graphite raw material is subjected to first-stage heat preservation treatment at the temperature T1 in advance, and a first-stage material is obtained; grinding and grading the first-section material to obtain graphite powder A and graphite powder B; then shaping and grading the graphite powder A to obtain graphite powder C; mixing the graphite powder B and the graphite powder C to obtain graphite powder D; the graphite powder D is subjected to liquid phase treatment in acid liquor in advance, and graphite powder E is obtained; the graphite powder E is subjected to two-stage gas-solid treatment with gas control and pressure control, and the nuclear-grade natural graphite is prepared. According to the method, the purity of the graphite can be obviously optimized, and in addition, the loss of strength in the purification process can be avoided, so that the graphite which is more than 5N, ultralow in nuclear reaction degradation impurities, excellent in strength and capable of meeting the application requirements of a nuclear reaction device can be obtained.

The invention relates to the field of biomedical application of inorganic materials, in particular to application of lanthanum carbonate in preparation of drugs for resisting liver cirrhosis and inhibiting liver inflammations, the drugs comprise lanthanum carbonate and pharmaceutically acceptable auxiliary materials, the drugs are ground and then mixed with food to prepare a drug mixture, and the drug mixture is prepared into the drug for resisting liver cirrhosis and inhibiting liver inflammations. The mass ratio of the lanthanum carbonate in the medicine mixture is 1-10%, and the mechanism of the lanthanum carbonate for treating the liver cirrhosis is as follows: interference or blocking of activation and proliferation of hepatic stellate cells, inhibition of extracellular matrix generation and promotion of extracellular matrix degradation. According to the invention, a rat liver cirrhosis model is constructed through chemical induction, and the effects of reversing liver cirrhosis and inhibiting liver inflammation are found when a rat is treated by taking lanthanum carbonate orally, so that a new candidate drug is provided for clinical treatment of liver cirrhosis.

The invention relates to the field of nuclear power, in particular to a control method for natural oxidation of a primary loop of a nuclear power plant. The method comprises the following steps: carrying out primary loop dissolved hydrogen control; primary loop nitrogen purging hydrogen removal; and the primary loop is naturally oxidized. The method is suitable for a VVER unit, the activity concentration of the activated corrosion product in a primary loop main system is reduced, deposition of the activated corrosion product on the surface of main equipment is reduced, and therefore the radiation dose field level in the unit maintenance period is reduced, and the irradiation dose of workers in the radioactive environment is reduced.

The invention relates to the field of intelligent medical treatment, in particular to a radioactive monodisperse particle preparation, aerosol generation and animal inhalation deposition in-situ quantification method. Comprising the following steps: acquiring aerosol generation standard particles and radioisotopes; adding the standard particles and radioactive isotopes into a PBS solution, and carrying out an oxidation-reduction reaction to obtain a reaction solution; the reaction solution is washed and filtered through deionized water until no separable gamma activity exists, and the radioactive standard particles used for aerosol generation are obtained.The radioactive aerosol generation particles with the single particle size can be obtained and have good clinical value.

The present disclosure provides a process for the separation and purification of radium and actinium from acidic solution using composite adsorbents. The process includes preparing polyoxometalates (POMs)-based mesoporous composite metal-infused resins using phosphate recovered from waste buffer solution. The resins are prepared using a modified sol-gel technique to form inorganic composite metal-oxide clusters. Embodiments of the resins include silica-coated composite metal oxide particles, including antimony-vanadium oxide particles, and tungsten-doped mesoporous titanium oxide particles. The resins have differing adsorption affinities for actinium, radium, and other metal ions and may thus be utilized for selectively separating radium and actinium from irradiated thorium targets.

The invention discloses a design method of a hydrogen recombiner arrangement scheme in a nuclear power plant containment. The design method comprises the following steps: step 1, determining the total number of hydrogen recombiners; step 2, determining the number of the hydrogen recombiner in the compartment: step 2-1, selecting a serious accident sequence; 2-2, carrying out risk analysis on the selected serious accident sequence, and determining a hydrogen risk compartment; step 2-3, carrying out sensitivity analysis on the number of the hydrogen recombiner in the risk compartment, and determining the number of the hydrogen recombiner in the compartment; and step 3, determining a hydrogen recombiner arrangement scheme according to the total number of the hydrogen recombiners and the number of the recombiners in each compartment. The method can be used for guiding the scheme arrangement of the hydrogen recombiner, solves the problem of lack of a standard design process of the arrangement scheme of the hydrogen recombiner in the prior art, and improves the effectiveness of the arrangement scheme of the hydrogen recombiner, thereby avoiding the processes of slow combustion, fast combustion, fire blast, explosion and the like after a serious accident occurs in a nuclear power plant, and guaranteeing the integrity of a containment.

Systems and methods for generating radionuclides, such as radium-224, are disclosed herein. Systems herein may include a first cartridge having a first opening, a second opening, and a chamber therebetween having a first resin having affinity for thorium-228 and bismuth-212; a second cartridge having a first opening, a second opening, and a chamber therebetween having a second resin having affinity for thorium-228, a third cartridge having a first opening, a second opening, and a chamber therebetween comprising a third resin having affinity for thorium-228 and bismuth-212, and a fourth cartridge having a first opening, a second opening, and a chamber therebetween having a fourth resin having affinity for lead-212; wherein a continuous flow path is formed from a top of the first cartridge though the second cartridge, through the third cartridge, and to a bottom of the fourth cartridge during system use.

The invention belongs to the technical field of nuclear power data processing, and particularly relates to a multi-level data cleaning method for the nuclear power industry. Comprising a first hierarchy data importing and preprocessing layer, and the first hierarchy is a basic unit for nuclear power multi-hierarchy data cleaning; the second level carries out local processing layer data processing, and the data subjected to secondary cleaning is recompressed, feature codes are extracted, and then the data are transmitted to the third level; or directly forwarding the unprocessed original compressed data; the third hierarchy carries out data processing of the platform layer in the data; and the fourth level performs data processing of the data application layer, and is responsible for performing persistent storage on the data according to a standardized format after the data is subjected to full-process cleaning, compression, feature extraction and desensitization processing. The method has the beneficial effects that the method is specially customized for the nuclear power industry: special requirements of high confidentiality, network isolation, large data volume and the like of data in the nuclear power industry are fully considered, and a special cleaning and desensitization process is designed.

The invention relates to the technical field of radiopharmaceutical preparations, in particular to yttrium [90Y] microsphere injection as well as a preparation method and application thereof. The preparation method of the yttrium [90Y] microsphere injection comprises the following steps: S1, uniformly mixing a radioactive stock solution and an yttrium sulfate solution, stirring and mixing with resin microspheres, and washing to obtain yttrium [90Y] microspheres; s2, stirring and mixing a sodium phosphate solution and the yttrium [90Y] microspheres, taking out 1 / 3 volume of clear liquid, carrying out suction filtration on the residual clear liquid, and mixing the taken clear liquid with the yttrium [90Y] microspheres to obtain mixed liquid; and S3, stirring and mixing the sodium dihydrogen phosphate solution and the mixed liquid, taking out 4 / 10 volume of clear liquid, carrying out suction filtration on the residual clear liquid, mixing the taken clear liquid with yttrium [90Y] microspheres, washing, filling and sealing, and sterilizing to obtain the yttrium [90Y] microsphere injection. The labeling rate of yttrium [90Y] in the produced yttrium [90Y] microsphere injection is high.

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.

Described is a method for evaluating oil recovery. The method includes performing a pre-coreflood process, a coreflood process, and a post-coreflood process. The pre-coreflood process includes preparing heterogenous cores samples with different structural configurations. The coreflood process includes injecting a treatment into the core samples and obtaining nuclear magnetic resonance (NMR) measurements of the treated core samples. NMR measurements are compared to assess performance of the treatment. The post-coreflood process includes conducting an X-ray micro-computerized topography (CT) scan and a Saturate, Aromatic, Resin, and Asphaltene (SARA) analysis on the treated core samples.

The present invention provides a fluorine-containing accelerator and a preparation method thereof, relating to the technical field of accelerator preparation. The fluorine-containing accelerator comprises the following weight percentages: liquid sodium aluminate: 8-15%; aluminum sulfate: 40-50%; fluoride salt: 6-9%; alcoholamine: 4-8%; and water: 25-32%; the sum of these components being 100%. The fluorine-containing accelerator does not produce particle precipitation during preparation, making the preparation process easy to operate.

The embodiment of the invention discloses a composite shielding plate and a preparation method thereof, and the composite shielding plate comprises a cladding which is provided with an accommodation space, and the accommodation space is in a vacuum state; the shielding material is arranged in the accommodating space; wherein the shielding material comprises a neutron moderation base material, and the cladding is made of a boron-containing metal material; or the shielding material comprises a neutron moderation base material and a neutron absorption base material, the cladding is made of a metal material, the neutron moderation base material comprises rare earth hydride, and the neutron absorption base material comprises boron-containing ceramic. The composite shielding plate provided by the embodiment of the invention not only comprises the neutron moderation base material which is high in hydrogen content and excellent in temperature resistance so as to effectively moderate fast neutrons, but also is combined with the neutron absorption base material containing boron atoms so as to efficiently absorb thermal neutrons, so that the complete neutron moderation-absorption integrated shielding performance of the composite shielding plate is realized; and stable shielding performance can be provided at the temperature of 300-1000 DEG C.