1054 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 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 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 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 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 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.

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.

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

The 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.

The invention provides a nuclear power hole shielding design method and system. The method comprises the following steps: acquiring a formatted data set; performing radiation environment judgment to obtain a hole radiation environment data set; basic parameter calculation is carried out to obtain hole shielding design basic parameters; performing preliminary decision generation to obtain a first hole shielding design decision parameter; correcting the first hole shielding design decision parameter to obtain a second hole shielding design decision parameter; performing plugging optimization to obtain shielding plugging engineering parameters; and integrating the second hole shielding design decision parameter and the shielding plugging engineering parameter to obtain a hole shielding design result. According to the method, formatted data sets are obtained, analysis and judgment are automatically carried out based on the data sets, all steps are classified and modularized according to the shielding design judgment principle, input and output elements between modules are defined, the informatization technology is applied, automation and batch design of nuclear power hole shielding design are achieved, and the design efficiency is greatly improved.

The present application relates to a kind of preparation method of bismuth trifluoride, belong to bismuth compound preparation technical field.The preparation method of bismuth trifluoride of the present application includes the following steps: bismuth-containing compound powder is hydrothermally reacted with hydrofluoric acid;The bismuth-containing compound is one or any combination of bismuth oxide, bismuth oxychloride, bismuth trichloride.The preparation method of bismuth trifluoride of the present application carries out hydrothermal reaction to bismuth oxide, bismuth oxychloride, bismuth trichloride and hydrofluoric acid, and the high temperature and high pressure generated by hydrothermal reaction are used to improve the reactivity, solve the problem that bismuth oxide, bismuth oxychloride and bismuth trichloride are not completely reacted with hydrofluoric acid under normal pressure, resulting in low yield and low purity, product can be obtained by one-step reaction.The preparation method of bismuth trifluoride of the present application is simple, and route is short, the solvent used is water, cost is low, yield is high, and it is economic and environmental protection.

The invention relates to the technical field of yttrium sol preparation, in particular to yttrium sol and a preparation method and application thereof. The preparation method of the yttrium sol provided by the invention comprises the following steps: adding yttrium salt into water, stirring and dissolving to obtain a solution A, and then adding glacial acetic acid into the solution A, stirring and dissolving to obtain a solution B; ethylene glycol is added into the solution B for a reaction, and yttrium sol is obtained; wherein the mass ratio of the yttrium salt to the glacial acetic acid to the ethylene glycol is (7-9): 1: 1. According to the invention, glacial acetic acid is used as a chelating agent and is matched with ethylene glycol to prepare the yttrium sol, so that the solid content and the stability of the yttrium sol can be improved.

Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

The present invention belongs to the technical field of evaluation methods, and specifically relates to a method for evaluating the configuration of mobile equipment in a nuclear power base based on multi-unit safety evaluation. The method comprises the following steps: Step 1: Modeling the mobile equipment, using PSA software to add the mobile equipment to the event tree and fault tree of the single-unit PSA model, and analyzing the time of mobile equipment intervention and personnel reliability events; Step 2: Using PSA software to establish a MUPSA model; Step 3: Setting up a sensitivity analysis case and performing calculations; Step 4: Using the calculation results to analyze risk changes and preliminarily select a configuration plan; Step 5: Combining factors such as configuration maintenance cost, availability, and comprehensive emergency dispatch to conduct a multi-objective comprehensive optimization analysis and further screen the configuration plan; Step 6: Based on the screened configuration plan, an evaluation of the existing configuration of the nuclear power base and configuration recommendations are given. The beneficial effect is that it can effectively solve the problem of a lack of sufficient theoretical analysis basis and a lack of a systematic and effective configuration evaluation method when configuring mobile equipment in nuclear power bases.

Systems and methods for generating radionuclides, such as radium-224. 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 and bismuth-212, 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, a fourth cartridge having a first opening, a second opening, and a chamber therebetween having a third 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 relates to the technical field of nuclear power safety, and discloses an ink screen display device with an inspection function for nuclear power safety, which comprises an environment sensing module, an autonomous inspection module, an ink screen display module, a data processing and communication module and a power management module, and the ink screen display device has hardware composition and software functions. According to the ink screen display device with the inspection function for nuclear power safety, through an automatic inspection process and real-time data display, the workload of inspection personnel is reduced, the inspection efficiency is improved, a low-power-consumption and high-contrast ink screen technology is adopted, it is ensured that information can be clearly displayed under the condition that light is weak in a nuclear power facility, and the inspection efficiency is improved. The safety of inspection personnel is improved, the accuracy and reliability of inspection data are ensured by collecting and transmitting environmental parameters in real time, powerful support is provided for nuclear power safety management, the inspection efficiency and the data accuracy are improved, and powerful guarantee is provided for nuclear power safety management.

The invention relates to the technical field of niobium-tantalum-iron ore purification, in particular to a method for preparing high-purity tantalum pentoxide and niobium pentoxide from niobium-tantalum-iron ore. The method comprises the following steps: firstly, adding ammonium fluoride and ammonium sulfate to help mineral decomposition and reduce the roasting temperature, then treating the niobium-tantalum iron ore by using a sulfuric acid-hydrofluoric acid mixed solution to fully dissolve niobium-tantalum oxides, then extracting and separating niobium and tantalum by using a specific solvent system, and finally adding ammonia water to precipitate and calcine to obtain the niobium-tantalum iron ore. The high-purity niobium pentoxide and tantalum pentoxide are prepared, the product yield is high, the impurity content is low, and the niobium pentoxide and tantalum pentoxide are suitable for being used as raw materials of capacitor-grade tantalum powder and niobium powder.

The invention is suitable for the technical field of nuclear reactor safety of a nuclear power plant, and provides an efficient nuclear reactor safety margin evaluation method and system, terminal equipment and a computer program product, and the method comprises the following steps: constructing a training data set based on a sample data set of uncertainty parameters and time sequence data of key safety parameters; training the initial agent model based on the training data set to obtain a target agent model; the sequence overrun probability of the key safety parameters is efficiently calculated through the target agent model; and calculating the shutdown risk of the nuclear reactor based on the sequence overrun probability and taking the shutdown risk as a safety margin assessment result of the nuclear reactor. According to the method provided by the invention, the sequence overrun probability of the key safety parameters is efficiently calculated, and the shutdown risk of the nuclear reactor is calculated based on the sequence overrun probability and is used as the safety margin evaluation result of the nuclear reactor, so that the safety margin of the nuclear reactor is efficiently, quickly and accurately evaluated.

The invention belongs to the technical field of degassing membrane degassing devices of nuclear power plants, and discloses an assembly tool and an assembly method for a degassing membrane degassing device of a nuclear reactor. The assembly tool comprises a first tool body, a second tool body and a fastening assembly. Wherein the height of the portion, stretching into the end face of the outer shell, of the first pressing part is larger than the height of the portion, stretching into the end face of the outer shell, of the second pressing part, and the height of the second pressing part meets the requirement that when a final pressing position is reached, the second pressing part is pressed; the length of the part, extending into the outer shell, of the second pressing part is consistent with the length of the part, extending into the outer shell, of the gland assembly of the outer shell. The first tool and the second tool which are matched with each other achieve staged assembly of controllable pre-pressing, ejection ring mounting, symmetrical final pressing and precise centering on sealing assemblies at the two ends of the hollow fiber membrane column in the outer shell, and the good sealing effect is achieved.

A method for producing calcium phosphate crystals according to the present invention comprises a step (S11) for preparing a weakly basic phosphoric acid solution containing a complex comprising a rare earth element ion and a coordination compound having a ligand coordinated to the rare earth element ion and a step (S12) for adding a calcium-containing compound to the weakly basic phosphoric acid solution and hydrolyzing. Some of the plurality of calcium ions contained in the structure of the calcium phosphate crystals are substituted by the rare earth element ion.