25 results about "Heavy water" patented technology

To provide a hydrogen isotope separation system capable of achieving stabilization of operation.SOLUTION: A hydrogen isotope separation system 10 comprises an electrolyzer 12, a separator 14, a coupler 15, a circulation flow passage 10e, a pump 18, and a control device 21 which controls the pump 18. The electrolyzer 12 performs electrolysis upon water including heavy water. The separator 14 separates a hydrogen isotope which is discharged from the electrolyzer 12. The coupler 15 generates power with light hydrogen which is discharged from the separator 14. The circulation flow passage 10e connects an anode supply path 10a and an anode discharge path 10c which are provided with respect to an anode 15b of the coupler 15 to which the light hydrogen is supplied while detouring the coupler 15. The pump 18 circulates fluid from the anode discharge path 10c toward the anode supply path 10a in the circulation flow passage 10e.SELECTED DRAWING: Figure 1

The invention belongs to the technical field of nuclear energy equipment power supply design, and particularly relates to a power supply protection and distribution unit circuit. The device comprises an outer box shell and a refrigeration inner container arranged in the outer box shell. The refrigeration inner container is provided with an air inlet and an air outlet, and an air flow channel is formed between the air inlet and the air outlet. A cross-flow fan is arranged at the air inlet and used for guiding waste gas into the air flow channel. A thermoelectric refrigeration piece is arranged in the refrigeration inner container, and a cold end fin is connected to the rear portion of the cold end of the thermoelectric refrigeration piece and used for condensing heavy water vapor in waste gas in the air flow channel, so that the problem that in the prior art, heavy water vapor contained in by-product oxygen during deuterium preparation through heavy water electrolysis is mostly and directly discharged along with oxygen, and the deuterium preparation efficiency is improved is solved. And heavy water is greatly wasted.

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.

The invention discloses a laser neutron yield increasing method based on a composite conversion target, which comprises the following steps of: arranging a plurality of elements to form the composite conversion target, bombarding the composite conversion target by using a deuterium ion beam obtained by interaction of laser and a heavy water liquid film target, and realizing neutron yield increasing through nuclear reaction section optimization; elements in the composite conversion target comprise at least two of T, D, < 7 > Li and < 9 > Be. According to the laser neutron yield increasing method based on the composite conversion target, the neutron yield and the average flux of a repetition frequency laser neutron source method are greatly increased, and the problem of instability in the continuous production process of a heavy water liquid film target is solved.

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.

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.

This invention discloses a method for detecting hydrogen deuteride after water-hydrogen isotope liquid-phase catalytic exchange. The apparatus used in this method includes a first Erlenmeyer flask, a metering pump, a catalytic exchange bed, a flow meter, and a time-of-flight mass spectrometer. The detection process is as follows: a mixture of heavy water and purified water is filled into the first Erlenmeyer flask; a hydrophobic catalyst and hydrophilic filler for the isotope exchange reaction are filled into the catalytic exchange bed; the mixed water enters the catalytic exchange bed from the top and undergoes an isotope exchange reaction with hydrogen gas entering from the bottom of the bed; the deuteride gas after the exchange reaction is directly introduced into the time-of-flight mass spectrometer for detection via the flow meter. This method can monitor the changing trend of deuteride gas after water-hydrogen isotope liquid-phase catalytic exchange online. Simultaneously, the performance of the catalyst, the packing ratio, and the packing method can be examined, thereby further guiding the process. This method features fast analysis speed and high sensitivity.

The invention belongs to the technical field of isotope preparation, and particularly relates to a system and method for producing hydrogen isotopes with low energy consumption. The embodiment of the invention provides a system and a method for producing hydrogen isotopes with low energy consumption. The system comprises a power supply, a first storage tank, a steam generation heater, a heat recovery solid oxide tank, a gas-water condensation separator, a second storage tank, a gas cylinder storage tank and a purification separation column, heavy water in the first storage tank enters a steam generation heater to be heated into heavy water steam, and then enters a heat recovery solid oxide tank to be continuously electrolyzed and heated; and the cathode electrode of the heat recovery solid oxide tank generates high-temperature deuterium gas, and finally high-purity deuterium gas is separated and produced through the purification column. Due to the design of heat exchange, the heat loss of the system is reduced, the technological process is simple and efficient, the utilization rate of raw materials is increased, good economic practicability is achieved, the problem of high energy consumption in the application process of the solid oxide technology is solved, the product cost is reduced, and industrial application is promoted.

The invention discloses equipment, a system and a method for online extraction of enriched heavy water through coupling of an alkaline electrolytic bath. The equipment comprises an alkaline electrolysis unit, a deuterium-enriched water extraction unit and a gas-liquid separation and water regeneration unit, a cascade enrichment system is formed by connecting multiple stages of electrolysis enrichment devices in series, online and step-by-step concentration of deuterium isotopes in raw material water is achieved, and therefore product water with the high deuterium enrichment degree is obtained.

The application relates to the technical field of nuclear reactors, in particular to a supercritical carbon dioxide cooling pressure tube type reactor and application thereof. The reactor comprises: a moderator container containing heavy water, and a radial reflection layer covering the radial periphery of the moderator container; a plurality of tubes immersed in the heavy water in the moderator container; a plurality of pressure tubes coaxially arranged in the tubes one by one, and the pressure tubes have coolant channels for circulating supercritical carbon dioxide; a fuel assembly arranged in the pressure tube; and a reactivity control assembly arranged in the radial reflection layer. Through the matching of the heavy water moderation characteristics and the gadolinium-based poison absorption characteristics, the reactivity consumption of the reactor in a long operation period is smoothly compensated, so that the micro reactor can realize long-period operation without replacing the fuel under the condition of not more than 25% low enrichment.

The application discloses a method and device for detecting bubbles in heavy water, electronic equipment and a storage medium. The method comprises: obtaining an absorption spectrum of a heavy water sample; determining a first concentration section to which the heavy water sample belongs based on the absorption spectrum of the heavy water sample; determining a first spectrum feature corresponding to the first concentration section; the first spectrum feature represents a wave number range of each flat-top peak in the absorption spectrum of a standard heavy water sample of the first concentration section; and determining whether the heavy water sample contains bubbles based on the first spectrum feature and the absorption spectrum of the heavy water sample.

A flow rate formation method for system decontamination of a heavy-water reactor nuclear power plant is provided. A nuclear power plant includes: a reactor; a first coolant pump disposed on one side of the reactor, a second coolant pump disposed on the other side of the reactor, and first coolant system piping passing through the reactor and connecting the first coolant pump and the second coolant pump; a first shutdown cooling pump disposed on one side of the reactor, and first shutdown cooling system piping branching from the first coolant system piping at a downstream end of the first coolant pump and connected to an upstream end of the first coolant pump through the first shutdown cooling pump; and a second shutdown cooling pump disposed on the other side of the reactor, and second shutdown cooling system piping branching from the first coolant system piping at a downstream end of the second coolant pump and connected to an upstream end of the second coolant pump through the second shutdown cooling pump, wherein the first coolant system piping, the first shutdown cooling system piping, and the second shutdown cooling system piping are decontaminated simultaneously by operating the first coolant pump and the second shutdown cooling pump and stopping the second coolant pump and the first shutdown cooling pump.

The invention belongs to the technical field of nuclear fuel, and particularly relates to a heavy water reactor fuel rod bundle in-reactor damage monitoring method. Comprising the following steps: 1, carrying out online monitoring by using a fission gas monitoring system; 2, chemical sampling analysis of the coolant; and 3, performing data analysis by using a damaged fuel positioning system. The method has the beneficial effects that the method solves the problems that the monitoring means for the damage in the heavy water reactor fuel rod bundle is single, and the time for intervening in searching the damaged fuel is late, the fuel damage phenomenon can be found in the first time, and the work for searching the damaged fuel is started in the first time. The damaged fuel searching work is involved in advance, the searching time of the damaged fuel can be shortened, and the influence of coolant nuclide on personnel and the environment after damage can be reduced.

A target used for heavy water reactor production of C-14 isotopes, which comprises: a target tube, which has a target material (11) and / or an absorber material (14), the target material (11) being a nitrogen-containing solid material; end plates (2), which are arranged at two ends of the target tube; a connection rod (3), which is provided with a connection component that is connected to a positioning mechanism used for positioning the target, wherein the connection rod (3) passes through the target tube along the axial direction of the target tube, and the target tube is fixedly connected to the connection rod (3) by means of the end plates(2). The present invention can be adapted to be placed at different locations such as at a guide tube, an inspection passage, or a fuel channel to undergo irradiation and produce C-14 isotopes.

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.

The application discloses a kind of equipment and method for electrolytic concentration low-purity heavy water while producing high-purity deuterium gas.The equipment of the application includes electrolysis power supply (1), water tank (2), electrolytic cell (3), gas-water separation chamber (4), purification column (6), gas storage tank (7), thermometer (8), synthesis chamber (9), fire barrier (10), fire barrier (11), condensation chamber (14), buffer chamber (15), gas chamber (16), gas mixing chamber (17), water tank (18), cooling device (20), hydrogen gas-water separator (24), oxygen gas-water separator (25);The application utilizes sulfonated tetrafluoroethylene group fluoropolymer-copolymer membrane electrolytic cell to reduce the volume of electrolytic concentration low-purity heavy water, and the low-purity deuterium gas electrolyzed by reducing the volume is re-synthesized in synthesis chamber and condensed into heavy water, which improves the production efficiency of high-purity deuterium gas, and has excellent electrolysis effect and economy.

The invention discloses a system and a method for preparing high-purity deuterium gas based on electrolysis of heavy water in a solid oxide electrolytic tank. The system comprises a heavy water heating device, an SOEC reactor, a vertical tube furnace, a deuterium gas condensing device, an external power supply and a deuterium gas storage tank. The SOEC reactor is positioned in the vertical tube furnace, and two ends of the solid oxide electrolytic tank are connected with an external power supply. Heavy water is gasified through the heating device and then directly input into the cathode of the solid oxide electrolytic tank, heavy water vapor is electrolyzed into deuterium gas through external voltage, meanwhile, oxygen ions are generated, the oxygen ions are transmitted to the anode through electrolyte and oxidized into oxygen at the anode, and the purpose of preparing high-purity deuterium gas through heavy water electrolysis is achieved. According to the system, heavy water vapor is directly subjected to high-temperature electrolysis by using an SOEC technology, and high-purity deuterium gas can be obtained through a deuterium gas drying device. The method is high in operability, low in safety risk and easy for large-scale production, and solves the problems of high heavy water impurity removal cost, high low-temperature electrolysis energy consumption and low efficiency in the prior art.

The invention relates to a heavy water gradient enrichment method and system for coupling electrolysis of seawater to produce hydrogen, and belongs to the technical field of seawater resource utilization. The heavy water gradient enrichment method comprises the following steps: pretreating natural seawater to obtain pretreated seawater; the pretreated seawater is subjected to ALK electrolysis or AEM electrolysis, so that deuterium in pretreatment is preliminarily enriched to form deuterium-rich alkali liquor during hydrogen production; evaporating the deuterium-rich alkali liquor under the thermal driving of the primary electrolysis heat carried by the deuterium-rich alkali liquor to remove alkali and salt to obtain primary deuterium-rich pure water; performing PEM electrolysis on the primary deuterium-enriched pure water to form secondary deuterium-enriched pure water; and carrying out rectification treatment on the secondary deuterium-enriched pure water carrying the secondary electrolysis heat to obtain a heavy water product. According to the heavy water gradient enrichment method, through combination of coupling of different seawater electrolysis hydrogen production modes and rectification treatment, gradient enrichment of heavy water is achieved, energy consumption is low, enrichment efficiency is high, and the method can meet the requirement for large-scale heavy water extraction.

The present application relates to a kind of high-efficiency heat dissipation neutron target device for electron accelerator boron neutron capture therapy, it includes: electron beam control system, beam transmission vacuum pipeline, heavy water chamber, composite target, neutron beam reflector, shielding body and neutron beam slowing shaping body, wherein, electron beam control system is expanded to beam or the way of electron beam scanning is expanded to beam cross-sectional area;Beam transmission vacuum pipeline small diameter end is connected to the connecting flange of electron accelerator beam outlet;Heavy water chamber contains circulating heavy water;Composite target includes X-ray conversion target and high-efficiency heat exchange base, and the side of high-efficiency heat exchange base facing heavy water is provided with cooling array flow-through heavy water, increase the area of contact with circulating heavy water, increase the heat dissipation efficiency;Neutron beam reflector reflects the neutron emitted in different directions to the predetermined neutron beam exit;Shielding body, neutron beam is collimated to the shape and size required for treatment;Neutron beam slowing shaping body carries out neutron beam in exit slow spectrum shape optimization.

The invention relates to a method for measuring the molecular content of H2O, HDO and D2O in heavy water by using an attenuated total reflection infrared absorption spectrum, which comprises the following steps: assembling a device comprising a Fourier transform infrared spectrometer and an ATR (Attenuated Transform Resonance) component, enabling interference light to pass through a reflecting lens to a crystal, and reflecting to a detector after total reflection; preparing a series of initial concentration heavy water solution standard samples; standing or heating the standard sample to isotope exchange equilibrium, and calculating theoretical concentration; testing the standard sample to obtain the characteristic peak areas of 1640 cm <-1 > (H2O), 1200 cm <-1 > (D2O) and 2500 cm <-1 > (O-D), and making a standard curve; and testing a blind sample and substituting into the curve to obtain the content. According to the method, the problems that the O-H peak of the high-concentration water sample is saturated and the molecular morphology of HDO and D2O cannot be distinguished in the traditional infrared spectroscopy are solved, accurate quantification is realized, and a reliable molecular level detection means is provided for the fields of nuclear industry and the like.

The present application relates to a kind of methods for controlling the concentration of deuterium gas in heavy water reactor under severe accident, by arranging different types of deuterium gas elimination device in different compartment region of heavy water reactor containment, so that the deuterium gas concentration in different compartment region of containment is reduced, and the goal of eliminating the risk of deuterium gas in heavy water reactor containment under severe accident is achieved. The deuterium gas concentration in heavy water reactor containment under severe accident is controlled by using ignition device and catalytic composite device jointly. For the compartment region where the main heat transport system break, the discharge pipe container burst disc and the fluid release valve are located, the ignition device is arranged to rapidly reduce the deuterium gas concentration in the compartment; for other compartment region, catalytic composite device is arranged to eliminate the deuterium gas in other compartment region. The deuterium gas elimination technology of the present application can effectively control the deuterium gas concentration in heavy water reactor containment, thereby realizing the elimination of the risk of deuterium gas in heavy water reactor containment.

The embodiment of the application provides a method and system for extracting helium-3 in high tritium heavy water mixed gas. The method comprises purification treatment, low-temperature pre-fractionation treatment and dehydrogenation treatment. The method can extract helium-3 generated in the storage process of high tritium heavy water, provides a new way for obtaining helium-3, thereby improving the yield of helium-3. In addition, the method has the advantages of advanced process, high separation degree and high quality of helium-3 gas, and the helium-3 generated in the storage process of high tritium heavy water can be fully obtained, thereby improving the energy utilization rate.

The invention relates to a hot film coupling heavy water extraction method and system based on seawater electrolysis hydrogen production, and belongs to the technical field of seawater resource utilization. The method comprises the following steps: pretreating natural seawater to obtain pretreated seawater; the PEM electrolysis unit is used for carrying out electrolysis treatment on the pretreated seawater, and deuterium in the pretreated seawater is primarily enriched to form primary deuterium-enriched water during hydrogen production; primary deuterium-enriched water produced in the PEM electrolysis step is directly used as a feed of a raw material side of a membrane separation unit, in the membrane separation unit, the primary deuterium-enriched water is vaporized under thermal driving of electrolysis sensible heat carried by the primary deuterium-enriched water, light water enters a condensation side to be condensed through a separation membrane of the membrane separation unit, and heavy water is enriched on the raw material side to obtain secondary deuterium-enriched water; and rectifying the secondary deuterium-enriched water by using a rectifying unit to obtain a heavy water product. Through effective coupling of PEM electrolysis, membrane method isotope screening and rectification, extraction of commercial-grade heavy water is achieved under low energy consumption, and the heavy water enrichment efficiency is high.

To provide a gas production method capable of stably producing hydrogen gas, deuterium gas and oxygen gas, and also capable of producing the gases on site at a production site of a semiconductor product or the like.SOLUTION: The method for producing gaseous hydrogen, gaseous deuterium and gaseous oxygen by electrolysis of water includes obtaining gaseous oxygen, gaseous hydrogen and heavy water by solid polymer electrolyte membrane water electrolysis to which a water circulation system A is applied and obtaining gaseous oxygen and gaseous deuterium by subjecting the heavy water to solid polymer electrolyte membrane water electrolysis to which a water circulation system B is applied.SELECTED DRAWING: Figure 1

This invention provides a hydrogen isotope separation system that can suppress the decrease in separation capacity during startup. [Solution] The hydrogen isotope separation system 10 includes a separator 15 having an ion exchange membrane 15a, an anode 15b, and a cathode 15c. The hydrogen isotope separation system 10 includes an anode supply path 10a for supplying heavy water to the anode 15b and a cathode supply path 10b for supplying cathode gas to the cathode 15c. The hydrogen isotope separation system 10 includes a first heat transfer medium circuit 30, a second heat transfer medium circuit 40, and a control device 50. The control device 50 acquires the temperature of the separator 15 and each humidifier 14A, 14B after the heating of the separator 15 and each humidifier 14A, 14B by the first heat transfer medium circuit 30 begins when the system is started up. If the temperature of the separator 15 and each humidifier 14A, 14B is above a first predetermined temperature, the control device 50 cools each condenser 16A, 16B by the second heat transfer medium circuit 40.