1947 results about "Nuclear chemistry" patented technology

The invention belongs to the field of medical radioactive isotope preparation, and particularly relates to a method for extracting lead-212 and bismuth-212 from a thorium-232 decay chain, a solution containing a thorium-232 decay chain substance passes through an anion exchange resin column, the solution containing the thorium-232 decay chain substance contains halide ions, and the anion exchange resin column is used for extracting the lead-212 and the bismuth-212 from the thorium-232 decay chain substance. The concentration of hydrogen ions in the solution containing the thorium-232 decay chain substance is greater than 0.01 mol / L, the lead-212 and the bismuth-212 are adsorbed by the anion exchange resin column, other nuclides directly penetrate through the anion exchange resin column and are not adsorbed, a leaching reagent is introduced to desorb the lead-212 and the bismuth-212 from the anion exchange resin column, and the lead-212 and the bismuth-212 are separated and extracted; the method can be used for simultaneously extracting lead-212 and bismuth-212, has the advantages of high extraction speed and high purity, and is not easy to cause organic pollution to products.

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.

An integral molten salt nuclear reactor includes a drain tank section configured to hold a volume of fuel salt. The integral molten salt nuclear reactor further includes a reactor section configured to receive the volume of fuel salt from the drain tank and cause fission reactions that heats the molten salt. The integral molten salt nuclear reactor further includes a heat exchange section configured to receive a flow of the heated fuel salt from the reactor section and remove heat therefrom.

A molten salt reactor system may produce fission products, such as molybdenum-99, which may be extracted by an extraction system. The extraction system may be configured to sparge the molten fuel salt with an inert gas to dislodge gaseous fission products from the molten fuel salt, so that the gaseous fission products flow through an off-gas outlet into a gas transfer assembly. The example extraction system may also include introducing a gaseous halogenating agent to prevent the fission products from depositing on a pipe surface of the gas transfer assembly. The gaseous fission products may flow from the gas transfer assembly to a carboy containing an aqueous solution, to process and / or filter the fission products. The resulting solution containing processed fission products in the carboy may be further distilled into final, usable products.

The present disclosure discloses an integrated rapid treatment system for nuclear medical radioactive wastewater and an application method thereof. This system includes a wastewater collection unit; a pretreatment unit; a deep purification unit; a solid decay unit; a buffer unit; an online monitoring unit; and a control unit, wherein the online monitoring unit includes a radioactivity level detection module for detecting total α and total β radioactivity concentrations of inlet and outlet water of a medium in each unit, and a real-time monitoring module for treatment process parameters. The present disclosure discloses an integrated rapid treatment system for nuclear medical radioactive wastewater and an application method thereof, which can efficiently and quickly purify multi-nuclide organic low-level wastewater produced by a nuclear medical process, and realize rapid online monitoring and automatic control at the same time.

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 present invention is directed to a fission product extraction system operable to capture and extract fission products from a flow of irradiated fueled molten salt of a molten salt reactor. The example extraction systems described herein utilize electroless deposition to chemically plate fission products onto a metallic structure. The metallic structure may be partially coated with a reducing agent, such as beryllium to provide an electron source for the fission products. The metallic structure may be a component of an extraction system designed to facilitate submersion of the metallic structure into the flow of molten salt. The extraction system may also be designed to facilitate removal of the metallic structure without requiring a shut down or slowdown of the reactor system.

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 field of shielding materials, and provides lead-free rubber with ionizing radiation shielding performance and a preparation method thereof, and the lead-free rubber is mainly prepared from barium titanate / boron nitride composite filler, barium tungstate / boron carbide composite filler, tungsten powder, bismuth powder, a rubber matrix and an auxiliary agent according to a proportion. The barium titanate particles are uniformly loaded on the surface of the flaky boron nitride, so that the gamma ray and X ray shielding performance is improved, and meanwhile, the boron nitride provides excellent neutron shielding capability; barium tungstate particles are loaded on the surfaces of the boron carbide nanowires to form a multi-scale shielding network, and the shielding effect of neutrons and ionizing radiation is remarkably enhanced. The rubber matrix endows the material with excellent flexibility and mechanical properties. By scientifically optimizing the component proportion and the preparation process, the problems that a traditional high-density shielding material is prone to agglomeration, poor in flexibility and the like are solved, and the material shows excellent performance in the fields of gamma ray, X ray and neutron shielding and is suitable for the fields of nuclear energy, medical protection, industrial radiation protection and the like.

The invention provides a reactor building, an arrangement method thereof and a nuclear power station. The arrangement method of the reactor building comprises the following steps: dividing a vertical surface space of the reactor building into layers along the vertical direction, arranging a reactor pit and a containment pit on a third underground layer, and arranging a first loop main equipment compartment, a second loop main equipment compartment and a third loop main equipment compartment on a second underground layer and above the second underground layer. A high-position refueling water tank of the passive safety injection system is arranged in a high-position refueling water tank compartment of a first underground layer, so that water in the high-position refueling water tank can submerge a reactor pit and main equipment of a reactor coolant system under the action of gravity. The method comprises the following steps: arranging core equipment of a passive special safety system in a containment; a special safety system related to safety can resist external disasters by means of the containment, and meanwhile, the system does not need to be switched between the inside and the outside of the containment during operation, so that the reliability of the system is greatly improved.

Disclosed in the present invention is a tritium production module system in a reactor. The tritium production module system has a multi-layer structure distributed in the radial direction of the reactor, and the tritium production module system comprises a tritium production area and a circulation area, wherein the tritium production area comprises a tritium breeding material, the tritium breeding material interacting with neutrons to produce tritium elements; the tritium production module system is in fluid communication with the outside of the tritium production module system via the circulation area; the circulation area comprises a tritium pipeline, the tritium pipeline being used for circulation of a reactor coolant and a tritium-containing medium, and the tritium pipeline extending in the axial direction of the reactor; a plurality of holes are provided in a pipe wall of the tritium pipeline, and the tritium pipeline is in fluid communication with the tritium production area via the holes, thereby improving the ability and efficiency of tritium transfer in the tritium production module system.

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 application of Ackermania muciniphila Akk09 in preparation of an element absorption enhancer and a product of the Ackermania muciniphila Akk09, belonging to the technical field of microorganisms. The invention provides application of Akkermansia muciniphila Akk09 with the preservation number of CCTCC (China Center For Type Culture Collection) NO: M 20242401 in preparation of an element absorption enhancer and in preparation of a medicine for treating element deficiency, and further provides the Akkermansia muciniphila Akk09 containing the Akkermansia muciniphila Akk09 and the medicine for treating the element deficiency based on the application. The Akk09 provided by the invention can effectively promote the transport of iron ions, zinc ions and selenium ions and enhance the absorption of iron, zinc and selenium ions.

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 boron manganese tannate nanoparticle as well as a synthesis method and application thereof. The synthesis method of the tannic acid boron manganese nanoparticles comprises the following steps: sequentially dropwise adding a bivalent manganese salt solution, a boric acid solution, a polyethylene glycol solution and a bovine serum albumin solution into pure water under water bath ultrasonic or magnetic stirring to obtain an assembly stock solution, and adding a tannic acid solution into the assembly stock solution to initiate assembly; and continuously carrying out water-bath ultrasonic treatment or magnetic stirring for a period of time, and then carrying out ultrafiltration to remove free drug molecules, so as to obtain the boron manganese tannate nanoparticles capable of mediating boron neutron capture therapy and magnetic resonance imaging. The boron manganese tannate nanoparticles can improve the boron intake in tumors and prolong the retention time of boron atoms in the tumors in boron neutron capture therapy, drug distribution is monitored through the nuclear magnetic resonance imaging technology, then the treatment effect of the boron neutron capture therapy is improved, the preparation method is simple, the stability is good, the size is uniform, the boron loading amount is high, and the application prospect is wide. The biological safety is good, and the repeatability is high.

Embodiments of the present disclosure include an integral nuclear reactor having a core fluidly coupled to an inlet chamber and to an outlet chamber. In some instances, the nuclear reactor may include a hub to house the core, the chambers, and the protective plug. The hub may include a window allowing a heat transfer fluid to flow from the outlet chamber, through the hub, and enter an annular space between the hub and a separation shell. The heat transfer fluid may flow into an inlet of a heat exchanger. The heat transfer fluid may flow through the heat exchanger before exiting at a heat exchanger outlet. The heat transfer fluid may enter an annular delay tank before flowing down an annular downcomer duct formed by the separation shell being housed in a reactor vessel. The heat transfer fluid may flow from the annular downcomer duct and into the inlet chamber.

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 discloses a radionuclide-labeled polymer as well as a preparation method and application thereof. Specifically, the invention provides a radionuclide labeled polymer which has the following structure: G-L1-L2-P, wherein G is a radionuclide-containing group and comprises a chelating group and a radionuclide, the chelating group is chelated with the radionuclide, and L1 and L2 are independently chemical bonds or linking groups; p is a temperature-sensitive structural unit. The radionuclide-labeled polymer can be used as a tracer of hydrogel, can be combined with the hydrogel under the condition that the property of the hydrogel is not changed, has good compatibility and stability, and further can be used for tracing implanted hydrogel and continuously tracking the position and state of the implanted hydrogel in real time.

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 discloses a radioactive gas detection device and a detection method.The radioactive gas detection device is applied to detection of radioactive gas containing target nuclides and comprises an adsorption assembly, a sampling assembly, a monitoring assembly, a desorption assembly, a detection assembly, a first control valve set and a controller, the sampling assembly, the adsorption assembly and the monitoring assembly are sequentially communicated; the adsorption assembly is further communicated with the detection assembly, and the controller is configured to control the first control valve group to enable the adsorption assembly and the sampling assembly as well as the adsorption assembly and the monitoring assembly to be in a disconnected state when the monitoring assembly monitors that the radioactive gas passing through the adsorption assembly contains target nuclide; the adsorption assembly and the detection assembly are in a communication state, and the detection assembly is controlled to execute detection operation on the target nuclide released from the adsorption assembly so as to obtain the content of the target nuclide. The radioactive gas detection device can improve the detection precision of the target nuclide in the radioactive gas.

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 a hafnium-based adsorption material, a preparation method thereof and a method for removing thorium ions in nuclear waste liquid. The hafnium-based adsorption material comprises an MOF with hafnium ions as a metal center and ellagic acid as an organic ligand, and in an X-ray diffraction pattern of the MOF under CuK alpha radiation, at 5 degrees lt; 2 [theta] lt; and in the range of 20 degrees, four diffraction peaks at the positions of 5.0 degrees + / -0.3 degrees, 8.6 degrees + / -0.3 degrees, 13.2 degrees + / -0.3 degrees and 17.2 degrees + / -0.3 degrees exist. The hafnium-based adsorption material disclosed by the invention has improved adsorption capacity on thorium ions under the condition of low pH value.

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 a common glass curing method for radioactive incineration ash and a contaminated glass fiber filter material, which comprises the following steps of: melting and curing a raw material containing the radioactive incineration ash and the contaminated glass fiber filter material by adopting a method I or a method II to prepare a glass cured body; according to the first method, raw materials of the filter material containing the radioactive incineration ash and the contaminated glass fiber comprise 0 wt%-30 wt% of the radioactive incineration ash and 70 wt%-100 wt% of the contaminated glass fiber filter material, and the melting temperature ranges from 1100 DEG C to 1400 DEG C; according to the second method, raw materials of the filter material containing the radioactive incineration ash and the contaminated glass fiber comprise 0 wt%-40 wt% of the radioactive incineration ash, 30 wt%-60 wt% of the contaminated glass fiber filter material and 15 wt%-50 wt% of an additive, and the melting temperature ranges from 900 DEG C to 1300 DEG C. According to the method, the glass solidified body meeting the disposal requirement can be effectively and stably obtained on the premise that the incineration ash component fluctuates greatly and the fly ash component contained in the contaminated glass fiber filter material is uncertain.

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.