684 results about "Nuclear chemistry" patented technology

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 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 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 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.

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 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.

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 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.

The present application relates to a kind of methods for separating actinium from irradiated thorium target, belong to medical radioisotope manufacturing technical field, solve the problem that thorium element and lanthanide element impurity content in final actinium product in prior art is higher.The present application discloses a kind of methods for separating actinium from irradiated thorium target, first, irradiated thorium target is dissolved, then using cation exchange resin column, UTEVA or TK200 resin extraction column, DGA resin extraction column, LN resin extraction column four-stage series separation purification process, obtain final actinium product.Actinium is efficiently and selectively recovered, and the thorium element and lanthanide element impurity content in final actinium product is significantly reduced.

The present disclosure generally relates to materials, processes, generators, and / or systems, for generating radioisotope. The present disclosure also generally relates to ceramic materials comprising radioisotope suitable for use in a radioisotope generator. The present disclosure also generally relates to processes, generators and / or systems, for producing and capturing radioisotope. The present disclosure also generally relates to the preparation of radioisotope solutions for use in radiopharmacy and / or other clinical applications.

The invention relates to the technical field of iodide content detection, in particular to a method for determining radiochemical purity and iodine content of sodium iodide capsules for diagnosis by HPLC (High Performance Liquid Chromatography), which comprises the following steps: setting chromatographic conditions, and connecting a radioactive flow detector and an ultraviolet detector in series; preparing a disodium hydrogen phosphate solution, a glucose solution, a vitamin C solution, a first control solution, a potassium iodate solution, a second control solution, a carrier solution, a first sample solution, a second sample solution, a negative control solution and a test solution; and determining the radiochemical purity and iodide content of the first sample solution and the second sample solution in three batches based on the chromatographic conditions and the determination standard. According to the method, test parameters such as capsule sample analysis time, a pretreatment mode and a sample size are optimized, the radiochemical purity of the capsule is accurately determined, and the iodide content is controlled, so that the problem that main components cannot be accurately quantified and potential radioactive impurities cannot be detected by a traditional diagnosis sodium iodide [131I] capsule determination method is solved.

The embodiment of the invention discloses an inorganic anti-neutron shielding material and a preparation method thereof. The inorganic anti-neutron shielding material comprises the following raw materials in percentage by weight: 5-60% of a base material; 1-90% of lightweight aggregate; 1-20% of a neutron shielding functional auxiliary agent; and 4-40% of water. The inorganic hydroxide is used as the lightweight aggregate, so that the density of the filling aggregate is greatly reduced, the overall weight of the shielding material is reduced, and meanwhile, the phenomenon that the aggregate sinks when separated from cement due to the fact that the gravity is too concentrated due to the too large specific gravity of the aggregate is avoided. In addition, the inorganic anti-neutron shielding material provided by the invention has good neutron shielding performance and mechanical properties. The invention can further enrich the variety and application range of the shielding material, and has important strategic significance and positive social significance.

The invention relates to an ultra-pure calcium fluoride crystal raw material and a preparation method thereof. The preparation method of the hyperpure calcium fluoride CaF2 crystal raw material comprises the following steps: (1) respectively weighing a calcium source and a fluorine source according to the stoichiometric ratio of elements in CaF2, and carrying out vacuum drying to remove adsorbed water and bound water so as to obtain a dehydrated calcium source and a dehydrated fluorine source; (2) mixing the dehydrated calcium source, the dehydrated fluorine source and absolute ethyl alcohol, and carrying out ball milling to obtain a white pasty mixed raw material; and (3) carrying out vacuum high-temperature heat treatment on the white pasty mixed raw material, carrying out solid-phase reaction on calcium ions and fluorine ions to generate calcium fluoride, cooling after the reaction is finished to obtain white powder, and grinding and crushing to obtain the ultra-pure calcium fluoride crystal raw material.

The invention discloses a radioactive medical isotope Ra-223 stably-labeled rare earth nano diagnosis and treatment preparation as well as a preparation method and application thereof. According to the invention, by constructing a dual protection mechanism of the shell layer and the functional biomolecular layer, the Ra-223 is effectively packaged, the recoil nuclei of the Ra-223 are reserved at the tumor part and are prevented from escaping to the surrounding environment of the tumor, the safety of the Ra-223 treatment process can be enhanced, the radioactive energy is ensured to accurately act on the focus, and the treatment effect of the Ra-223 is improved. Meanwhile, the damage risk to healthy tissues is minimized.

The invention relates to a zirconium and hafnium extraction agent as shown in a formula I, an extraction system and a method for separating and purifying zirconium and hafnium. The zirconium and hafnium extraction agent shows excellent zirconium and hafnium separation performance and is suitable for efficient separation and high-purity preparation of zirconium and hafnium. According to the zirconium and hafnium separation and purification method, stable preparation of high-purity zirconium and hafnium products with the purity not lower than 99.99% is achieved. (I)

Methods for processing metal components from the nuclear industry are described. In some embodiments, a method includes processing a component having a surface contaminated with radionuclides by dissolving at least a portion of the surface with an acid solution to produce a waste solution including the radionuclides, and separating the radionuclides from the waste solution. In some embodiments, a method includes processing a component including a target radionuclide by immersing at least a portion of the component in an electrolyte bath, applying an electric current to cause electrodissolution, and electroplating the target radionuclide from the solution onto a cathode. In some embodiments, a method includes processing a metal composite component by dissolving it to produce a solution including dissolved metal and particulate material, and separating the particulate material.

The invention provides a radioactive substance transportation monitoring system, and relates to the technical field of radioactive substance transportation safety monitoring. The radioactive substance transportation monitoring system comprises a transfer protection box and a monitoring unit integrated on the transfer protection box, and the monitoring unit is composed of a double-detector fusion module, a three-dimensional data linkage analysis module and an active emergency disposal module which are sequentially connected through a circuit. The double-detector fusion module comprises a GM counting tube and a scintillator detector which are arranged inside and outside the box so as to realize alpha, beta, gamma and neutron multi-nuclide coverage; the three-dimensional data linkage analysis module performs comprehensive judgment based on internal and external doses of the box, temperature and humidity and vibration data, and accurately identifies protection failure or article leakage; and the active emergency disposal module automatically starts gate closing and adsorption measures in an emergency. According to the system, the problems of monitoring blind areas, reduced protection performance, frequent false alarm, emergency passivity and the like are solved, and the transportation safety and the intelligent level are improved.

The invention provides a reactor internal capable of realizing integral movement of a reactor core, and relates to the technical field of research, development and design of reactor body structures, the reactor internal comprises a hanging basket barrel, a reactor core shroud and a reactor core; the reactor core is arranged in the reactor core shroud; the reactor core shroud is arranged in the hanging basket barrel body, the reactor core shroud is movably connected with the hanging basket barrel body, the reactor core shroud slides up and down in the hanging basket barrel body, and the bottom of the hanging basket barrel body supports the reactor core shroud. According to the invention, the material changing and maintenance efficiency can be effectively improved, the downtime is shortened, the safety is enhanced, the personnel radiation exposure risk is reduced, the inspection and maintenance are convenient, and the service life of equipment is prolonged. The system adapts to advanced reactor design and conforms to the development trend of modularization and high efficiency, and the performance, safety and economical efficiency of the nuclear reactor are remarkably improved through the design of the system.

The invention discloses a tritium removal method for tritium-containing wastewater, which comprises the following steps of: reacting the tritium-containing wastewater with carbon under a high-temperature condition, transferring tritium from HTO to gaseous HT, and separating the HT to realize tritium removal. The invention also discloses a tritium removal device for the tritium-containing wastewater, which is used for the method. According to the invention, tritium-containing wastewater tritium removal and purification treatment with low construction cost and low operation cost can be realized.

The invention relates to a nuclear power system equipment nuclear safety performance evaluation method, which comprises the following steps of: obtaining a complete system list of a power plant, and screening the system list according to a nuclear safety function correlation condition to obtain a function list meeting a nuclear safety function requirement; classifying the function list based on the operation state to obtain a category system classification of the nuclear safety related system equipment meeting the operation state classification standard; performing performance index making according to the category classification to obtain a performance index making result of the nuclear safety related system equipment; and performing nuclear safety performance evaluation on the nuclear safety related equipment in the preset time period according to the performance index formulating result to obtain a nuclear safety performance evaluation result in the preset time. Through systematic equipment screening and classification, scientific and reasonable performance index formulating and dynamic performance evaluation based on actual operation data, the nuclear safety performance of the nuclear safety related equipment in the preset time period is evaluated; and refined evaluation of nuclear power plant system equipment nuclear safety performance is realized.

Provided is an inorganic fiber or inorganic flake having excellent neutron shielding properties. A formulation composed of a base component in which SiO2 and Al2O3 are the main components (in which the total mass ratio of SiO2 and Al2O3 in the base component is 0.60 or more) and a neutron shielding component composed of at least one of gadolinium, gadolinium oxide, samarium, samarium oxide, cadmium, or cadmium oxide is prepared in a ratio of 50 to 90 parts by mass of the base component and 10 to 50 parts by mass of the neutron shielding component, and then melted, thereby obtaining a good amorphous inorganic fiber and inorganic flake.

Provided is a method for producing a solution of atropine with improved recovery. A method for producing a solution of atropine-211, comprising the steps of: irradiating bismuth with alpha rays, generating atropine-211 in the bismuth, and distilling the bismuth irradiated with the alpha rays, separating and purifying atropine-211, and dissolving it in an aqueous sodium bicarbonate solution.

The application discloses an environmental functional nanometer material, a preparation method thereof and application of the environmental functional nanometer material in treatment of fluorine-rich radioactive nuclear wastewater, and relates to the technical field of environmental functional nanometer materials. The application discloses an environmental functional nanometer material, a preparation method thereof and application of the environmental functional nanometer material in treatment of fluorine-rich radioactive nuclear wastewater, and relates to the technical field of environmental functional nanometer materials.

The invention discloses a coated yttria-90 loaded radioactive microsphere and a preparation method and application thereof, and relates to the technical field of radioactive microsphere preparation, and the preparation method comprises the following steps: preparing a polyvinyl alcohol microsphere by using a microfluidic technology; the preparation method comprises the following steps: labeling polyvinyl alcohol microspheres with yttrium-90 radionuclide to obtain yttrium-90 loaded radiation microspheres; and coating the polylactic acid-glycolic acid copolymer on the surface of the yttria-90 loaded radioactive microsphere to obtain the coated yttria-90 loaded radioactive microsphere. The composite radioactive microspheres with uniform particle size, stable radioactivity and controllable characteristics can be obtained, and the composite radioactive microspheres are expected to be applied to transcatheter arterial radioembolism (TARE) treatment of liver cancer.

The present disclosure provides a novel method for producing a calcium salt. The preparation method of the calcium salt provided by the technical scheme of the invention comprises the following steps. And step S20, carrying out acid treatment on the raw material containing calcium phosphate to obtain an acid extracting solution. And S30, mixing the obtained acid extracting solution with alkali to obtain calcium phosphate precipitate. And S40, mixing the obtained calcium phosphate precipitate with acid and / or salt thereof to form calcium salt.

Described herein is a process for recovering uranium tetrafluoride (UF4) from hexafluoride uranium (UF6), the process comprising dissolving UF6 directly in an ionic liquid and recovering UF4, which can be processed to obtain UO2(s) or metallic uranium.

The invention relates to a method for separating heavy metal cations and radionuclides from aqueous solutions. The method according to the invention can be used to separate dissolved and / or suspended naturally occurring ions or radioactive ions produced by radioactive decay, nuclear transformation reactions such as nuclear fission, or, for example, by activation with neutron radiation, from aqueous solutions.