59 results about "Heavy water" patented technology

The invention relates to the field of heavy water production, and discloses a compression cycle heat supply heavy water rectification process which comprises the following steps: 1, carrying out primary rectification on feed water; 2, condensing tower top steam by a first-stage cooler to obtain tower top produced liquid, enabling one part of the produced liquid to flow back to a first-stage rectifying tower, discharging the other part of the produced liquid, pressurizing and heating a working medium heated by the first-stage cooler by a compressor, and feeding the working medium into a first-stage reboiler; 3, feeding one part of deuterium-enriched water of the tower kettle into a first-stage reboiler, boiling, returning to the bottom of the rectifying tower, taking the rest part as feed water for next-stage rectification, and returning a working medium cooled by the first-stage reboiler into a first-stage cooler through a first-stage expansion valve to be heated and evaporated; and 4, performing N-stage rectification and purification until the heavy water meets the purity requirement. By utilizing the characteristics that the boiling difference between water and heavy water is extremely small and the condensation heat of the tower kettle is equivalent to the heat source required by the tower kettle, the condensation heat of tower top steam is transferred to the tower kettle through the circulating working medium, the energy consumption is greatly reduced, and a large amount of heat sources can be provided for the system by a small amount of power consumption of the compressor.

The invention belongs to the technical field of heavy water reactor core flux detectors, and aims to solve the problems that the manual flux detector installation speed is low, the personnel irradiation dose is high, and the detector is easy to damage. The invention discloses a heavy water reactor core flux detector installation device and method, the device comprises a front guide pipe and a rear guide pipe which are coaxially arranged, the rear end of the front guide pipe is installed at a reserved installation position of a driving system shell, and a driving pair wheel set is arranged between the front guide pipe and the rear guide pipe; the driving pair wheel set is in transmission connection with the driving motor; the rear guide pipe is in butt joint with a detector reel bin, a reel is installed in the detector reel bin, the tail of the flux detector is clamped into the reel, and a flux detector cable is wound on the reel. According to the method, components of the device are used for installing the device, the heavy water reactor core flux detector installation device is removed, and flux detector installation is completed. The installation speed of the flux detector can be increased, the radiation dose of personnel is reduced, and the probability that the detector is prone to damage is reduced.

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 discloses a method and system for synchronous detection of carbon dioxide and semi-heavy water in the field of environmental detection. The method comprises: determining a first online wavelength for differential detection of carbon dioxide and a second online wavelength for differential detection of semi-heavy water and an offline wavelength shared by the two based on the absorption spectrum line obtained from the HITRAN database; calculating an estimated value of the concentration of semi-heavy water in the atmosphere according to meteorological data; determining a semi-heavy water concentration threshold suitable for semi-heavy water detection based on the second online wavelength and the offline wavelength according to a preset semi-heavy water concentration error and meteorological data; judging whether the current atmosphere meets the semi-heavy water detection conditions according to the semi-heavy water concentration threshold and the estimated semi-heavy water concentration; if so, performing synchronous detection of atmospheric carbon dioxide and semi-heavy water according to the first online wavelength, the second online wavelength and the offline wavelength to obtain the carbon dioxide concentration and the semi-heavy water concentration. The present application realizes synchronous detection of carbon dioxide and semi-heavy water based on coherent laser radar.

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.

The invention relates to a method for measuring the deuteration rate of heavy water by nuclear magnetic resonance hydrogen spectroscopy, which comprises the following steps: S1, weighing 0.03-0.08 g of sodium acetate or potassium acetate solid, adding into a beaker, adding 3-8g of heavy water into the beaker, fully shaking up, and taking the mixed liquid into a nuclear magnetic tube; s2, putting the nuclear magnetic tube into a nuclear magnetic resonance spectrometer, testing at normal temperature, and determining hydrogen spectrum chemical shift and hydrogen spectrum area of the heavy water and the sodium acetate according to a nuclear magnetic hydrogen spectrogram; and S3, quantitatively calculating the deuteration rate in the heavy water. According to a traditional mass spectrometry method, before the deuteration rate of heavy water is detected, heavy water and metal need to react, deuterium gas is generated, and then detection is conducted through high-resolution mass spectrometry, and the process is complex and long in consumed time. Compared with the prior art, the method has the advantages that the heavy water is directly detected by adopting the nuclear magnetic resonance hydrogen spectrum method, additional chemical reaction and gas treatment steps are not needed, and the operation process is obviously simplified, so that the detection efficiency is improved.

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 invention belongs to the technical field of deuteration rate detection, and particularly relates to a low-deuteration water deuteration rate detection method, which comprises: 1) preparing a heavy water standard sample with a known deuteration rate, carrying out a nuclear magnetic hydrogen spectrum test, and recording the water peak area; (2) estimating the deuteration rate of the deuterium-depleted water sample to be detected, then mixing a proper amount of the deuterium-depleted water sample with a proper amount of the heavy water standard sample, and preparing a mixed heavy water sample with the estimated deuteration rate of 98% or above; (3) carrying out nuclear magnetic hydrogen spectrum test on the mixed heavy water sample, recording the water peak area, and calculating the deuteration rate by using the water peak area according to an external standard method; and (4) calculating the deuteration rate of the deuterium-depleted water sample. The detection method overcomes the defect that a nuclear magnetic resonance hydrogen spectrum method cannot accurately measure the deuterium-depleted heavy water (deuteration rate lt; the deuterium content in a high range (more than or equal to 98%) is difficult to detect, the limitation that an external standard method can only detect the isotope abundance (more than or equal to 98%) of deuterium in a relatively high range is broken through, and meanwhile, the method is high in analysis precision and accuracy, low in equipment investment, simple and convenient to operate and low in analysis cost.

The invention relates to the technical field of heavy water concentration measurement, in particular to an infrared spectrum heavy water concentration measuring instrument which comprises a sample dilution unit, a temperature control unit, a light path unit, a colorimetric pool unit and a detector unit. Injecting the mixed sample into a colorimetric pool unit; the colorimetric pool unit comprises a standard solution colorimetric pool and a sample colorimetric pool, and the sample colorimetric pool is used for heavy water concentration detection; the temperature control unit is used for controlling the temperature of the sample dilution unit and the colorimetric pool unit; the light path unit is used for emitting infrared light to the sample colorimetric pool; and the detector unit is used for controlling the functions of other units and detecting the concentration of the heavy water sample in the sample colorimetric pool. The device realizes the functions of automatically analyzing the heavy water concentration, controlling the heavy water concentration measurement temperature, automatically calibrating the device by adopting a standard sample solution and the like.

A liquid target system (1) for producing radioactive isotopes, the liquid target system (1) comprising a boiling chamber (2) for containing a liquid and a base chemical by which a radioactive isotope can be produced by radiation, the boiling chamber (2) comprising a radiation window for effecting radiation on the liquid and the base chemical, causing the liquid to evaporate into vapor, wherein the liquid target system is configured such that the superheating of the liquid target (8) is controlled by the thermodynamics of the evaporation process, wherein the liquid is water or heavy water, and the base chemical is a salt having a positive enthalpy with respect to water.

A method for treating to-be-treated water containing tritiated water and light water, the method includes providing a temperature difference in a heavy water gas hydrate substrate which may contain tritiated water, and to-be-treated water containing tritiated water and light water in the presence of a guest molecular gas based on a heavy water gas hydrate crystallization temperature zone and its vicinity under a pressure condition where heavy water gas hydrate or tritiated water gas hydrate can be crystallized.

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 present invention provides a method and system for extracting helium-3 from a heavy water moderator gas mixture. The extraction method includes a purification process, a cryogenic pre-distillation process, a cryogenic distillation process, and a dehydrogenation process. The extraction method of the present invention can extract helium-3 produced by tritium decay in the heavy water moderator, providing a new approach for obtaining helium-3 and thereby increasing helium-3 production. Furthermore, the helium-3 extraction method of the present invention has the advantages of an advanced process, a high degree of separation, and high-quality helium-3 gas. The helium-3 produced during the operation of the heavy water reactor can be fully recovered, thereby improving energy utilization.

The invention particularly relates to a drainage and water filling operation method for a single fuel channel of a heavy water reactor nuclear power station. The drainage and water filling operation method comprises the following steps that 1, nuclear fuel in the fuel channel is emptied; 2, a fuel channel closure tool is installed to achieve closure; 3, ice plug isolation is carried out to carry out fuel channel drainage operation; 4, installing a temporary shielding plug to establish a maintenance condition; step 5, filling water into a fuel channel; and step 6, reloading the nuclear fuel in the fuel channel. According to the method, necessary conditions are established for fault processing of the single fuel channel; meanwhile, after fault processing is finished, operations such as fuel channel water filling and nuclear fuel reloading are carried out, and the standard configuration of a single fuel channel is recovered; therefore, safe and smooth maintenance is ensured, operation risks are reduced, working efficiency is improved, and personnel radiation safety and reactor safety are ensured.

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.

This invention relates to the field of isotope production using the vertical flux detector channel of a heavy water reactor. Addressing the problems of inefficient isotope production using the vertical flux detector channel of a heavy water reactor, and the simultaneous production of multiple isotopes, this invention provides a target for isotope production using the vertical flux detector channel of a heavy water reactor. Several inner target tubes are arranged inside an outer target tube. The outer target tube has upper and lower end plugs at both ends. A metal wire is attached to the upper end plug to allow the target to enter or exit the reactor core through the vertical flux detector channel. The inner target tubes are loaded with at least one target material to produce at least one isotope. This invention has a simple structure, is easy to manufacture, and can achieve mass production of short-half-life medical isotopes such as lutetium-177, strontium-89, and holmium-166 using the vertical flux detector channel of a heavy water reactor.

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 provides a multi-membrane coupling process for extracting helium-3 from headspace mixed gas of a high-tritium heavy water tank, and belongs to the fields of chemistry and chemical engineering. The multi-membrane coupling process takes gas membrane separation technology as a core, and is coupled with catalytic oxidation and low-temperature condensation technology, so that the helium-3 is concentrated efficiently, and the heavy water, deuterium gas and argon gas are fully reused; simulation results show that the concentration of the helium-3 special gas can be increased from 1.0 mol% to more than 95.0 mol%, the single-pass recovery rate is more than 17.5%, the cyclic recovery rate is more than 99.8%, at the same time, the reuse rate of the argon gas is more than 99.8%, and the total reuse rate of the heavy water and the deuterium element is more than 99.95%.

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.

This invention relates to the field of isotope production technology, aiming to solve the problem that existing control rod structures cannot be completely disassembled in a water pool and can only be used for the irradiation production of cobalt isotopes. This invention provides a heavy water reactor control rod for the production and testing of multiple isotopes. The heavy water reactor control rod can be disassembled in the water pool attached to the heavy water reactor nuclear power unit. After disassembly, components for different purposes can be loaded into different transport containers for transport. This invention also provides a method for carrying out the production and testing of multiple isotopes on a heavy water reactor. This invention can realize the production and testing of multiple isotopes.