97 results about "Tritium" patented technology

Main characteristic of the invention is the exploitation of the very large flux of high energy neutrons generated in a nuclear fusion tokamak with beam-driven plasma for the purpose of producing radioisotopes. It specifically relates to the deployment of precursor materials into the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of Deuterium (D) and Tritium (T) to generate radioactive isotopes, so-called radioisotopes. The precursor materials contained in metallic capsules are incorporated into the blankets that surround the plasma.

The invention belongs to the technical field of tritium removal pump sets, and discloses a molecular pump set for evacuating a hydrogen isotope-containing super-large cavity, which comprises a stainless steel closed cavity and a super-large vacuum cavity, and is characterized in that a first tritium removal pump set and a second tritium removal pump set are respectively arranged in the stainless steel closed cavity through a fixing frame; the first tritium removal pump set and the second tritium removal pump set each comprise four tritium removal pumps, and the first tritium removal pump set and the second tritium removal pump set are integrally arranged in parallel and both communicate with the ultra-large vacuum cavity. According to the invention, the eight tritium removal pumps are mounted in the stainless steel chamber, and a connection mode of'parallel connection + series connection 'is creatively adopted, so that the requirement of continuous evacuation of the large chamber is met. In the initial stage, the eight tritium removal pumps operate in parallel so as to improve the overall pumping speed, the latter four tritium removal pumps serve as backing pumps, and the other four tritium removal pumps serve as main pumping pumps so as to improve the compression ratio of pumped tritium, increase the pressure of an exhaust port and improve the pumping efficiency of tritium.

The invention relates to the technical field of engineering logging, and discloses a low-power-consumption radio frequency ion source logging neutron tube and a working method, deuterium gas is ionized into deuterium ions through an ion source, the deuterium ions are accelerated under the action of a strong electric field to obtain energy, and the high-energy deuterium ions bombard a deuterium / tritium target to generate nuclear reaction to generate neutrons. The power requirement of the radio frequency source can be greatly reduced. Compared with an inductive coupling type radio frequency ion source neutron tube, the capacitive coupling type neutron tube has the advantages that D1 + 1 in plasma is increased to 50%, the required power is 25%-30% of that of the inductive coupling type neutron tube, the load of a neutron generator is greatly reduced, the D-D deuterium neutron tube is further applied to engineering practice, and powerful technical support is provided for green and environment-friendly well logging.

The application discloses a fusion reactor solid-state blanket design method based on topology optimization, and is characterized in that based on the topology structure characteristics of the fusion reactor solid-state blanket arranged in layers along the radial direction, the coupling mechanism of the multi-physical fields of neutronics, thermal-hydraulics and structural mechanics is researched, a coupling model between various parameters of the multi-physical fields is established through theoretical analysis and a multivariate nonlinear regression method; under the constraint conditions of material temperature and structural mechanical properties, a constrained topology optimization model for maximizing the tritium breeding ratio is constructed; the constrained topology optimization model is converted into an unconstrained topology optimization model for maximizing the tritium breeding ratio by using a Lagrange function and a KKT condition, the unconstrained topology optimization model is solved by using a gradient descent algorithm, and a blanket radial topology structure capable of meeting the design criteria is obtained. A blanket three-dimensional model is established, and the performance of neutronics, thermal-hydraulics and structural mechanics in the whole reactor is analyzed, the tritium production, heat removal and structural safety performance of the blanket are evaluated, and it is verified that the topology optimization model can efficiently obtain a blanket design scheme with optimal comprehensive performance of multiple fields.

This invention discloses a method for producing radioactive isotopes in the core of an advanced high-temperature reactor using a spherical target. This invention overcomes the limitations of using neutron irradiation channels or fuel-related components of nuclear reactors, such as conditioning rods in heavy water reactors and combustible poison rods in pressurized water reactors, to produce radioactive isotopes. It sets a precedent for the mass production of radioactive isotopes using the core of a nuclear reactor, and has significant strategic implications for exploring high-value applications of commercial advanced high-temperature reactors to reduce operating costs and mass-produce radioactive isotopes, including the strategic isotope tritium.

The application provides an automatic sampling and measuring device for radioactive aerosol and gaseous tritium in radioactive gaseous effluent. The measuring device comprises a radioactive aerosol measuring module and a gaseous tritium measuring module integrated in the measuring device, and the radioactive aerosol measuring module and the gaseous tritium measuring module are communicated with a gaseous effluent pipeline through sampling pipelines. The measuring device of the application can greatly save labor, realize unattended and long-time online monitoring, flexibly adjust the sampling and monitoring frequency, and improve the monitoring efficiency. In addition, in the case of a nuclear accident, the emergency monitoring mode can be quickly started to quickly respond to the accident monitoring requirements, so as to realize continuous, online and automatic monitoring of the concentration of radioactive aerosol and gaseous tritium in the effluent of a nuclear facility.

The invention discloses a method for producing radioactive isotopes in a reactor core of an advanced high-temperature reactor by adopting a spherical target piece. According to the invention, the limitation that the radioactive isotope can only be produced by using a neutron irradiation channel of a nuclear reactor or fuel-related components such as an adjusting rod of a heavy water reactor and a burnable poison rod of a pressurized water reactor is broken through, and a precedent of mass production of the radioactive isotope by using the reactor core of the nuclear reactor is created; the method has important strategic significance for exploring high-value application scenes of commercial advanced high-temperature reactors to reduce operation cost and producing radioactive isotopes including strategic isotope tritium in batches.

This invention relates to a vertical oxidation-combustion collection system for sediment or biological radioactive organic carbon-tritium samples and its method of use, comprising: a vertical oxidation-combustion device for oxidizing and combusting the sample and catalyzing it into products to be separated; and a sample collection device comprising: a water vapor trapping module for collecting tritium samples; and a carbon trapping module for collecting... 14 Sample C; A rear-mounted protection module is used to discharge exhaust gas, collect waste liquid, and prevent external air interference with sample collection. This invention, by placing the collection port below the collection container, allows for the collection of tritium samples from combustion products under gravity. 14 Sample C is collected more thoroughly and can also prevent tritium from entering. 14 C-sample collection module, to avoid 14 Sample C enters the post-protection module; more importantly, nitrogen blowing or inert gas blowing can completely remove and collect any residual tritium sample in the collection module. 14 Like C, avoid the occurrence of the memory effect.

A metal-organic framework coating may be employed in a molten salt reactor system to capture gaseous fission products produced as a consequence of operation. The metal-organic framework coating may include one or more metal-organic frameworks configured to capture certain fission products based on the need, for example tritium fluoride, tritium gas, and hydrogen fluoride. The one or more metal-organic frameworks may be immobilized onto a substrate and formed into a coating covering the substrate. In many cases, the substrate is the stainless-steel surfaces of reactor enclosures and vessels. In other cases, the substrate may be suspended into a headspace of a vessel of a salt-bearing component, or may be included in an off-gas processing system of a reactor system.

The application discloses a fusion reactor liquid blanket tritium breeding rate online regulation system simulation method and device, wherein the simulation device comprises a fusion blanket neutron transport module, a blanket breeding agent Monte Carlo-activation coupling burnup simulation module, a blanket coolant feeding module, a blanket tritium extraction module, a blanket coolant purification treatment module, a blanket tritium breeding rate calculation module and a blanket tritium breeding agent circulation system; the simulation device realizes the circulation of the blanket coolant nuclide based on the mass conservation equation and the burnup equation. The application is based on the Boltzmann neutron transport equation, the neutron flux of the blanket coolant is simulated by a Monte Carlo method, the time and space variation law of the chemical composition of the system material is obtained by solving the burnup equation, the replenishment demand of the blanket coolant system is calculated, and the influence of the replenishment composition on the blanket tritium breeding rate is simulated, so that the application can be widely applied to the fusion reactor liquid lithium lead blanket.

The invention relates to the technical field of isotope batteries and discloses a nanopore-containing power generation assembly. The nanopore-containing power generation assembly comprises a transduction layer, the loading layer is arranged on the surface of the transduction layer in advance, and the loading layer is provided with preset nanopores. The technical problem that in the preparation process of the radioactive source in the isotope battery, due to the fact that the hydrogen absorption temperature of a hydrogen storage material is high, large thermal mismatching exists between a transducer device and the hydrogen storage material, growth stress is generated in the phase change process, and consequently the transducer device may have serious structural damage can be solved; the loading layer arranged on the surface of the transduction layer in advance is adopted, and the loading layer is provided with the nanopore structure, so that when the loading layer serves as a basic structure for preparing the isotope power generation assembly, for example, nanopores are filled with radioactive gas such as tritium, the loading layer structure is stable, and the isotope power generation assembly is prepared. The probability that the energy conversion layer structure is damaged due to growth stress generated in the phase change process can be reduced, and then it is guaranteed that the structure of the prepared isotope power generation assembly is stable.

The invention provides an automatic sampling and measuring method for gaseous tritium, which comprises the following steps: S1, sampling of tritium-containing gas: dissolving the tritium-containing gas in sampling liquid through a tritium-containing gas sampling unit to prepare tritium-containing liquid; s2, tritium-containing liquid sample preparation and sample feeding: tritium-containing liquid and scintillation liquid are proportionally injected into a measuring bottle through a tritium-containing liquid sample preparation unit, and then the moving position of the measuring bottle is controlled through a sample feeding operation unit; and S3, automatic measurement: measuring the flicker spectrum of the measurement bottle placed in an automatic measurement unit through the automatic measurement unit, and calculating the activity of tritium after measurement. According to the invention, automatic sampling, automatic sample preparation, automatic sample feeding and automatic measurement of tritium in air can be realized, automatic online monitoring of gaseous tritium is realized, and improvement of monitoring efficiency is facilitated; unattended operation and long-time full-automatic sampling and measurement of tritium in the atmospheric environment and gaseous effluent can be realized, and on-line monitoring of low-concentration tritium in air is realized; the system can be quickly started when a nuclear radiation accident occurs, and the response speed of nuclear emergency monitoring is improved.

This invention discloses a nano-alloy neutron target film material and its preparation method. The chemical formula of the target film material is Ti. a X b V c Al d Nb e Where X is selected from Zr or Mg, and a, b, c, d, and e represent the atomic percentages of the corresponding elements, with 5 ≤ a ≤ 40, 5 ≤ b ≤ 40, 5 ≤ c ≤ 40, 5 ≤ d ≤ 40, and 5 ≤ e ≤ 40, and a + b + c + d + e = 100. This invention, through rational composition design, coordination of multiple elements, and specific preparation methods, nanoscales high-entropy alloys, achieving a deuterium (tritium) release temperature of the neutron target exceeding 200°C, while simultaneously increasing the deuterium storage capacity H / M to over 1.8, effectively improving the temperature resistance and deuterium storage performance of the neutron target.

The invention provides an automatic sampling, sample preparation and measurement device and method for radioactive aerosol and gaseous tritium in radioactive gaseous effluent. The measuring device comprises a radioactive aerosol measuring module and a gaseous tritium measuring module which are integrated in the measuring device, and the radioactive aerosol measuring module and the gaseous tritium measuring module are respectively communicated with a gaseous effluent pipeline. According to the measuring device, manpower is greatly saved, unattended and long-time online monitoring can be achieved, the sampling monitoring frequency can be flexibly adjusted, and the monitoring efficiency is improved. Besides, under the condition of a nuclear accident, an emergency monitoring mode can be quickly started, and the accident monitoring requirement can be quickly responded, so that continuous, online and automatic monitoring of the concentration of radioactive aerosol and gaseous tritium in the effluent of the nuclear facility is realized.

The present application particularly relates to a method for producing helium-3 from heavy water in a heavy water reactor, comprising: step 1, subjecting the heavy water in a moderator system of a heavy water reactor unit to negative pressure rectification to obtain concentrated high-tritium heavy water; step 2, subjecting the concentrated high-tritium heavy water in step 1 to beta decay to produce helium-3 raw gas; and step 3, subjecting the helium-3 raw gas in step 2 to active carbon adsorption, helium-argon separation and hydrogen isotope gas adsorption to obtain helium-3. The method for producing helium-3 from heavy water in a heavy water reactor avoids technical difficulties and high costs of helium-3 / helium-4 isotope separation, and has high technical maturity and good economy.

This invention discloses a method for accurately tracing geological hydrogen migration, belonging to the field of geological hydrogen exploration and migration tracing technology. The invention involves preparing stable hydrogen isotopes and radioactive tritium tracers with specific geochemical fingerprints and injecting them into target geological units; deploying a three-dimensional monitoring network including sensor arrays and automatic samplers to collect hydrogen concentration data and gas samples in real time; laboratory analysis to determine hydrogen isotope composition and rare gas concentrations, using an N2-He-Ar ternary diagram to identify gas sources and eliminate interference; integrating data and performing numerical simulations using migration control equations coupled with isotope fractionation effects, optimizing parameters through inversion algorithms; and generating a three-dimensional visualization map of hydrogen migration paths and a quantitative report based on the inversion results. This invention achieves a breakthrough in geological hydrogen migration from qualitative detection to quantitative tracking, significantly improving the reliability and accuracy of tracing, enabling real-time dynamic capture of the migration process, and providing precise decision-making basis for hydrogen exploration.

The invention relates to the technical field of nuclear facilities, and discloses a deuterium-tritium fusion device containing zoning method, device, equipment and medium, and the method comprises the steps: preliminarily dividing each tritium-related room into a plurality of tritium-related regions with different tritium containing grades based on a preset tritium-related concentration limit value; identifying a transition room between two tritium-related areas with adjacent spatial positions and adjacent tritium containing levels, and generating a plurality of different candidate zoning schemes by adjusting the tritium-related area to which the transition room belongs; for any candidate zoning scheme, determining system balance time of the candidate zoning scheme based on the space volume of each tritium-related region, the annual average tritium release rate and the preset net exhaust air rate; and identifying the shortest system balance time in each system balance time, and determining the candidate partitioning scheme corresponding to the shortest system balance time as a target partitioning scheme. The method has the beneficial effect that the dynamic response performance of the negative pressure ventilation system is optimized.

A fusion system uses optical pulse shaping to control a fusion reaction by manipulating the quantum state of fluid fuel. The fusion system includes a reactor assembly that accepts fusion reaction fuel (e.g., hydrogen, hydrogen deuteride, deuterium, or deuterium-tritium, liquid water, liquid 17O-heavy water, etc?), and provides for conversion of high-energy fusion products to current. The fusion system may operate at ambient or low temperature (relative to ambient conditions), in the infrared band of the electromagnetic spectrum (e.g., between 700nm and 16000nm), and at moderate field intensities (e.g., between 109W / cm2 and 1017W / cm2), enabling efficient use of compact femtosecond laser sources and in-line, passive, or active optical elements for ultrafast pulse shaping. The net result is a field-robust electrical generator assembly that may be seamlessly integrated into existing electrical infrastructures.

In order to realize a fuel breeding unit that does not require the introduction of tritium recovery piping, a fuel breeding unit (1) converts kinetic energy of neutrons generated by nuclear fusion in plasma into thermal energy and generates tritium using neutrons. The fuel breeding unit (1) discharges the generated tritium directly into the reactor.

A breeder blanket is disposed within a stellarator. The breeder blanket defines a breeder zone through which a particle and a flow gas flows. The particle interacts with a neutron generated by a fusion reaction within the stellarator to generate heat. The flow gas absorbs the heat. A separator at an outlet of the breeder blanket separates the flow gas from the particle. The heat in the flow gas is used to generate power.

The invention provides a method for reducing tritium emission of a pressurized water reactor unit, which comprises the following steps of: discharging a primary loop coolant into a refueling water tank in a containment vessel for temporary storage for t time, reducing tritium concentration in the primary loop coolant by utilizing natural decay, and then discharging the primary loop coolant so as to reduce the tritium emission of the pressurized water reactor unit, the t time is a fuel circulation period of the pressurized water reactor unit. The method is reasonable in design and easy to operate, the primary loop coolant is temporarily stored through the refueling water tank in the existing containment, the tritium concentration in the primary loop coolant is reduced through tritium natural decay, tritium emission of the pressurized water reactor unit can be reduced, additional devices and equipment are not needed, and the tritium treatment cost of the pressurized water reactor unit cannot be increased.

The invention discloses a tritium monitor for realizing alpha, beta and gamma background deduction and a tritium activity concentration detection method.The tritium monitor comprises a detector I, a detector II and a signal processing unit, and the detector I is used for detecting alpha particles, beta particles and gamma particles; wherein the beta particles comprise tritium decay beta particles and high-energy beta particles with energy higher than that of the tritium decay beta particles, and the detector II is used for detecting alpha particles, gamma particles and high-energy beta particles and outputting signals II corresponding to counting rates of the particles. The signal processing unit is electrically connected with the detector I and the detector II, and the signal processing unit is configured to be used for receiving the signal I and the signal II, calculating a background equivalent current jointly generated by the alpha particles, the gamma particles and the high-energy beta particles based on the signal II and a preset calibration coefficient, and calculating the total ionization current based on the difference value of the total ionization current and the background equivalent current. And obtaining a net tritium current, and determining the tritium activity concentration based on the net tritium current.

The invention belongs to the field of neutron tubes, and particularly relates to a carbon nanotube cold cathode ion source neutron tube and a logging method based on the neutron tube. The neutron tube comprises a tube shell assembly, a core column assembly, a carbon nano tube cold cathode ion source, an acceleration system, a tritium titanium target assembly and a storage device. The tube shell assembly is a vacuum sealing shell of the neutron tube; the core column assembly is connected with the carbon nano tube cold cathode ion source, the anode assembly and the storage device, and power is supplied to the carbon nano tube cathode, the anode and the storage device through electrode leads on the core column assembly. The method has the advantages that the carbon nano tube cold cathode ion source and the carbon nano tube cathode belong to field emission cathode materials, and the electron emission speed of the carbon nano tube cold cathode ion source and the carbon nano tube cathode is in a nanosecond level, so that the ionization speed and the neutron explosion time can be ensured to be less than 1 mu S, stratum information can be acquired according to a measurement time sequence during well logging, and the accuracy of the stratum information is ensured; in addition, due to the fact that the density of the carbon nano tube array is large, the density of generated ion beams is large, and the yield of emitted neutrons is high.

Electrolysis induces cold fusion, producing helium-4. [Solution] A mixture of heavy water D and tritium T is placed in a container and electrolyzed using nickel and palladium electrodes to produce helium. The produced helium is collected in a container.

The present application relates to a kind of tritium separation method of tritium-containing wastewater and its reactor system, application, the tritium separation method of tritium-containing wastewater of the present application is ultraviolet irradiation promotes separation method, comprising: step 1) tritium-containing wastewater is introduced into the reaction containment of reactor system and is contacted with adsorption material to form liquid-solid two-phase contact system, step 2) after ultraviolet light is irradiated to liquid-solid two-phase contact system, make tritium enrich in adsorption material;Step 3) after the liquid-solid two-phase contact system of irradiation is completed, solid-liquid separation is obtained to low concentration tritium treatment water and tritium-rich adsorption material.The method of the present application is irradiated by ultraviolet light, accelerates hydrogen / tritium isotope exchange and adsorption process, can obtain higher tritium removal rate and adsorption amount under the same processing time.The present application belongs to energy-saving and environmental protection industry, especially in wastewater environmental control and nuclear pollution wastewater treatment in the environmental protection application of the recovery treatment of nuclear radioactive pollution elements plays a key role.

A method and a device for nuclear fusion with a deuterium alloy reactor are provided. The device includes: a high-energy neutron generator unit for generating a high-energy neutron current to bombard densely confined static deuterons in the deuterium alloy, producing high-energy deuterium nuclei; a deuterium alloy reactor unit, where deuterium gas forms a deuterium alloy upon entering the reactor, when bombarded by an external high-energy neutron current, high-energy deuterium nuclei are generated, the high-energy deuterium nuclei collide with tightly confined static deuterium nuclei in the deuterium alloy reactor, overcoming a Coulomb barrier and undergoing a nuclear fusion reaction; the high-energy deuterium nuclei further collide violently with the high-energy tritium nuclei produced by the nuclear fusion reaction to continue the nuclear fusion reaction; and an energy conversion unit configured to convert energy generated by the nuclear fusion reaction into usable energy.

The invention relates to the technical field of nuclear radiation monitoring, in particular to an automatic gaseous tritium sampling and measuring method which comprises the following steps: a feature space mapping step: acquiring ionization current and environmental data, and extracting multi-dimensional signal features; a memory entropy observation step: inputting the features into a dynamic memory entropy observer model, and resolving a current memory entropy value representing the nuclide adsorption degree; an intelligent decision-making step: generating an optimal sampling control strategy by using a reinforcement learning decision-making model based on the memory entropy; a dynamic regulation and control and output step: controlling the valve to be switched between a continuous sampling mode and a pulse cleaning mode in response to the strategy, and outputting a measurement result; by introducing the memory entropy state variable, the sensor is converted into an active gamer, and the effective service life of the sensor is prolonged to the maximum extent.

This application provides a steel material for reactors and a method for preparing the same. The steel material for reactors includes a steel substrate and a protective coating. The protective coating includes an in-situ oxide layer on the surface of the steel substrate and an alumina layer on the in-situ oxide layer. The in-situ oxide layer includes α-Fe₂O₃, and the alumina layer includes α-Al₂O₃. In the steel material for reactors, the α-Fe₂O₃ in the in-situ oxide layer serves as a growth template for the alumina layer. Through the mutual matching and induction effect of crystal structures, the protective coating forms a dense protective barrier on the surface of the steel substrate, effectively reducing the permeation of hydrogen and its isotopes deuterium and tritium.

The invention discloses a fusion reactor multi-working-condition full-range hydrogen isotope separation method, which adopts any mode of series connection and / or parallel connection of a plurality of low-temperature rectification systems, series connection and / or parallel connection of a plurality of low-heat cycle adsorption systems, series connection and / or parallel connection of the low-temperature rectification systems and the heat cycle adsorption systems aiming at multiple working conditions of a fusion reactor. The multiple working conditions of the fusion reactor comprise any one of deuterium and tritium gas separation with the tritium content larger than or equal to 1%, deuterium and tritium gas separation with the trace tritium content and ternary gas hydrogen-deuterium-tritium mixed separation. According to the invention, the series connection and parallel connection design of two hydrogen isotope separation processes is adopted, the requirements of treatment of different gases in the fusion reactor and material flow balance during continuous treatment are considered, and the requirement of continuous treatment of hydrogen isotope gases in the fusion reactor is realized.