63results about "Hydrogen isotopes" patented technology

A process for the hydrogenation of carbonyl compounds consisting of the following steps: (a) providing hydrogen with a molar share of deuterium ≤ 100 ppm, based on the total hydrogen content, by electrolysis of water using electrical power generated at least in part from non-fossil energy, (b) hydrogenating a carbonyl compound using the hydrogen provided in step (a) to form the corresponding hydrogenation product, wherein at least one carbonyl group of the carbonyl compound is hydrogenated.

The invention discloses a method for preparing deuterium-depleted water through cooperation of magnetic resonance and electrolysis strengthening, and particularly relates to the technical field of deuterium-depleted water preparation, and the method comprises the following steps: S1, injecting water to be treated into a magnetic resonance reaction chamber, and carrying out magnetic resonance treatment, so that the vibration energy level of a deuterium-oxygen bond is improved through a nuclear magnetic resonance effect, the bond energy is enhanced to 5.0-5.2 eV, and the deuterium-depleted water is obtained; forming a metastable-state deuterium-containing water molecular structure; s2, the water subjected to magnetic resonance treatment is guided into a three-electrode electrolytic bath for pre-electrolysis, then a gradient voltage electrolysis process is adopted for reinforced electrolysis to form a deuterium concentration gradient, and therefore hydrogen and electrolytic residual liquid are separated; and S3, finally performing gas-liquid isotope fractionation to finally prepare the deuterium-depleted water. According to the method, deuterium-oxygen bond energy is enhanced through magnetic resonance pretreatment, low-temperature gradient electrolysis and vacuum rectification are combined, a magnetoelectric synergistic isotope separation system is constructed, and the method has the advantages that the separation efficiency can be improved, the energy consumption can be reduced, the separation coefficient can be improved, the material utilization rate can be improved, and the deuterium content of the prepared deuterium-depleted water is lower than 30 ppm.

The invention relates to a membrane electrode and application thereof in deuterium-enriched water, and belongs to the field of clean energy development and utilization. The membrane electrode comprises a proton exchange membrane, an anode catalyst and a cathode catalyst, the anode catalyst is an iridium / iridium oxide catalyst with a three-dimensional porous network structure, and the cathode catalyst is a platinum-ruthenium alloy catalyst. The preparation method comprises the following steps: coating one side of the N117 proton exchange membrane with the anode catalyst, coating the other side of the N117 proton exchange membrane with the cathode catalyst, and then performing hot pressing to prepare the membrane electrode. The method comprises the following steps: assembling a membrane electrode into an electrolytic cell, and electrolyzing water by using the electrolytic cell to realize deuterium enrichment. The membrane electrode and the electrolytic cell are reasonable in design, the preparation process is simple and controllable, and the obtained product is high in efficiency and long in service life when used for enriching deuterium and facilitates industrial application.

The present invention relates to a process for hydrotreating feedstocks manufactured from plastic waste, such pyrolysis oils, using hydrogen having low deuterium content produced with non- fossil resources and energy, to the trackability of the hydrogen used in the hydrotreated feedstocks, and to hydrotreated feedstocks and downstream products thereof with depleted deuterium contents.

The application discloses a heavy water recovery device of a deuterium generator, which comprises a cooling box, a collecting box, a heat exchange device and a condenser pipe, an installation groove is arranged on the cooling box, an installation rod is arranged in the installation groove, an upper top groove is arranged on the installation rod, a positioning rod is arranged in the upper top groove through an upper top mechanism, positioning holes are arranged on the cooling box, a driving motor is arranged on the positioning rod, a driving gear is rotatably arranged on the upper end surface of the cooling box, the driving motor is connected with the driving gear through a clamping mechanism, and a screw rod is rotatably arranged on the cooling box through a supporting plate. The device is provided with a screw rod, a threaded sleeve, a connecting rod and a scraping ring, the water film on the inner wall of the condenser pipe can be scraped and collected, and the recycling effect of the reclaimed water is ensured; the device is provided with a driving gear, a transmission gear, a screw rod and a connecting rod, the synchronous movement of the two scraping rings is realized, and the transmission and linkage effects of the device are ensured.

A process for the preparation of amines comprising the following steps: (a) providing hydrogen with a molar share of deuterium ≤ 100 ppm, preferably in the range of from 10 to 95 ppm, more preferably in the range of from 15 to 90 ppm, most preferably in the range of from 20 to 80 ppm, especially in the range of from 30 to 75 ppm, based on the total hydrogen content, by electrolysis of water using electrical power generated at least in part from non-fossil energy, (b) reacting the hydrogen from step (a) with nitrogen to form ammonia, (c) reacting the ammonia from step (b) with a nitrile compound or hydrogen cyanide (I)         R-CN     (I) in the presence of hydrogen from step (a) to form the corresponding amine (II)         RCH2-NH2     (II).

To provide a deuterium recycling method and recycling apparatus that can recover and recycle deuterium (D2) contained in exhaust gases emitted from processes utilizing deuterium. [Solution] A method for recycling deuterium, comprising: a recovery step of recovering exhaust gas containing light hydrogen (H2) and deuterium, which is discharged from a process utilizing deuterium (D2), by contacting it with an adsorbent capable of adsorbing them; and a desorption step of desorbing light hydrogen and deuterium from the adsorbent. The desorption step includes a light hydrogen separation step carried out under a first condition in which light hydrogen is preferentially desorbed from the adsorbent, and a deuterium separation step carried out under a second condition in which deuterium is preferentially desorbed from the adsorbent. The method for recycling deuterium according to this disclosure includes a step of supplying the gas containing deuterium obtained in the deuterium separation step as a raw material gas in the process.

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 present invention is disclosed, belonging to the technical field of nuclear fusion raw material recovery. A cold trap recovery device for fusion reactor raw materials, a raw material recovery system and a method thereof according to the present invention include a cold trap recovery tower having a cold trap recovery chamber inside, and the cold trap recovery tower is provided with a fluid inlet, a gas outlet and a fluid outlet; a diversion recovery member vertically arranged in the cold trap recovery chamber of the cold trap recovery tower; a heating assembly for heating the diversion recovery member; at least one diversion inlet is provided above the diversion recovery member in the cold trap recovery chamber of the cold trap recovery tower, and at least one diversion outlet is provided below the diversion recovery member; the diversion inlet is opposite to the upper end of the diversion recovery member; the diversion outlet is opposite to the lower end of the diversion recovery member; along the length direction of the diversion recovery member, crystal capture members are protruded outward around its periphery. The main use of the present invention is to release the fuel particles retained in the liquid lithium and simultaneously purify the liquid lithium.

A process for the preparation of a cycloaliphatic or heterocycloaliphatic compound containing at least one aromatic or heteroaromatic ring comprising the following steps: (a) providing hydrogen with a molar share of deuterium ≤ 100 ppm, based on the total hydrogen content, by electrolysis of water using electrical power generated at least in part from non-fossil energy, (b) hydrogenating an aromatic or heteroaromatic compound using the hydrogen provided in step (a) to form the corresponding cycloaliphatic or heterocycloaliphatic compound wherein the at least one aromatic or heteroaromatic ring is partially or fully hydrogenated.

A process for the preparation of amines comprising the following steps: (a) providing hydrogen with a molar share of deuterium ≤ 100 ppm, based on the total hydrogen content, by electrolysis of water using electrical power generated at least in part from non-fossil energy, (b) reacting the hydrogen from step (a) with nitrogen to form ammonia, (c) reacting the ammonia from step (b) with a carbonyl compound (I)         R1R2C=O     (I) in the presence of hydrogen from step (a) to form the corresponding amine (II)         R1R2HC-NH2     (II).

This invention provides a hydrogen isotope separation system that can suppress increases in power consumption. [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 that supplies heavy water containing light water toward the anode 15b, and a cathode supply path 10b that supplies an inert gas toward the cathode 15c. The hydrogen isotope separation system 10 includes a heat transfer medium circuit 30 that supplies a heat transfer medium to an anode-side humidifier 14A located in the anode supply path 10a, a cathode-side humidifier 14B located in the cathode supply path 10b, and the separator 15. The heat transfer medium circuit 30 heats the anode-side humidifier 14A with the heat transfer medium after heating the cathode-side humidifier 14B.

This invention provides a deuterium ammonia production apparatus that enables economical and efficient production of deuterium ammonia using a flow system, without requiring a subsequent separation process that involves the supply of catalysts or large amounts of carrier gas. [Solution] A deuterated ammonia production apparatus having an absorption tower section consisting of one or more stages, the absorption tower section comprising a packing section consisting of packing material, an ammonia gas introduction section for introducing ammonia gas, a deuterated solvent introduction section for introducing a deuterated solvent, a deuterated ammonia gas discharge section for discharging deuterated ammonia gas, and a deuterated solvent discharge section for discharging deuterated solvent, wherein within the absorption tower section, the deuterated solvent flows downward through the packing section while the ammonia gas flows upward through the packing section, thereby causing the absorption of the ammonia gas into the deuterated solvent and an isotope exchange reaction to occur within the packing section, producing deuterated ammonia gas.

The application provides a catalytic regular packing structure for hydrogen-water isotope catalytic exchange and a preparation method thereof. The catalytic regular packing structure is divided into an embedded type and an integrated type. The hydrophilic packing of the embedded type includes at least two layers of hydrophilic packing sheets as a supporting skeleton; the hydrophobic catalyst is a granular, strip-shaped, pellet, cylindrical, Raschig ring or Michiyori ring hydrophobic catalyst particle, and the hydrophobic catalyst particle is at least partially arranged between adjacent hydrophilic packing sheets. The hydrophobic catalyst of the integrated type is a hydrophobic catalyst plate, and the hydrophilic packing and the hydrophobic catalyst plate are alternately placed according to the use ratio. The wall flow ring is arranged at the outer periphery of the hydrophilic packing; the hoop is arranged at the outer periphery of the wall flow ring, and the hydrophilic packing and the hydrophobic catalyst are wrapped and reinforced. The application provides a high-efficiency catalytic regular packing structure, which can effectively combine the hydrophobic catalyst and the hydrophilic packing, fix the gas phase channel and make the liquid phase uniformly dispersed, and can effectively avoid the amplification effect of the packing.

An apparatus (100) and method for integrated tritium extraction and recovery in a fusion power system is described. The technique comprises combining – in a tritium extraction unit (102) – a fluid tritium breeding composition (120) with a second fluid (122) to generate a combined fluid (110) undergoing two phase flow, and extracting tritium from the breeding composition in the two-phase flow by simultaneous processes of permeation across a solid membrane (118) and tritium transfer onto the second fluid (i.e., gas-liquid or liquid-liquid contacting). Also described is a corresponding fusion power system.

The present invention discloses a low-temperature plasma disproportionation reaction unit, which includes a U-shaped tube, and a double dielectric rod-cylinder type barrier discharge structure arranged on its straight pipe section, and a seal combining a double ceramic sheet and an organic insulating medium is provided at the top. A disproportionation reactor based on the reaction unit is also proposed, which mainly includes a filter, a flow controller, a first oxygen analyzer, a first buffer tank, a second oxygen analyzer, a low-temperature plasma disproportionation reaction unit, and a second buffer tank that are sequentially connected in series and located in a heat preservation layer. Finally, a disproportionation reaction method based on the disproportionation reactor is also proposed, which mainly includes purification, flow control, oxygen analysis to eliminate hydrogen explosion, low-temperature plasma disproportionation reaction, and gas component analysis to evaluate the reaction efficiency. The disproportionation reaction unit, reactor, and reaction method can achieve low-temperature disproportionation reaction, without the problems of noble metal catalyst shedding and tritium-containing waste generation, and at the same time have high conversion efficiency, fast reaction speed, and low operating cost.

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 application discloses an in-situ surface modification method for enhancing the CO2 and CO poisoning resistance of high-density metal-based alloy, which comprises the following steps: 1) carrying out surface modification on the activated dehydrogenated ZrCo-based alloy in a mixed gas of H2 and a modification gas at 350-450 DEG C; the modification gas is at least one of N2 and CO2; and 2) under the condition of dynamic evacuation, cooling the alloy processed in the step 1) to obtain a ZrCo-based alloy with CO2 and CO poisoning resistance. The application adopts the modification strategy of in-situ surface reconstruction, and solves the problem of poor CO2 and CO poisoning resistance of the ZrCo-based alloy. The application has the advantages of simple steps, low cost and high safety, and has important significance for promoting the application and popularization of the ZrCo-based alloy in the field of hydrogen energy.

This application discloses a fusion reactor ash gas treatment device, belonging to the field of fusion reactor technology. The fusion reactor ash gas treatment device includes: a shell forming a vacuum chamber; a gas supply unit for inputting ash gas into the vacuum chamber; an inductively coupled plasma generator for generating plasma from the ash gas input into the vacuum chamber; a hydrogen selective membrane disposed within the vacuum chamber, dividing the vacuum chamber into a first chamber and a second chamber; the inductively coupled plasma generator is at least partially located in the first chamber; deuterium ions and tritium ions pass through the hydrogen selective membrane into the second chamber and combine to form deuterium-tritium gas; a bias power supply electrically connected to the hydrogen selective membrane for applying a negative bias voltage; a first discharge section connected to the first chamber; and a second discharge section connected to the second chamber. This device achieves rapid treatment and recycling of the ash gas, is not only compact and easy to operate, but also reduces the amount of deuterium-tritium gas retained and energy consumption, improving operational reliability.

To inexpensively obtain gaseous deuterium from mixed gas of hydrogen and deuterium.SOLUTION: A first unit U1 formed mainly from an MEA M1 on an upper side functions as a fuel cell by generating a first reaction, and a D composition of input gas supplied to an anode side gas chamber 31 in the MEA M1 is concentrated. First discharge gas having an enhanced D / H composition ratio in the first input gas is discharged from a first gas chamber 31 of the MEA M1. A second unit U2 functions so as to further enhance D concentration of the first discharge gas. The first electrode 11 in an MEA M2 is electrically connected to the first electrode 11 in the MEA M1, and the second electrode 12 in the MEA M2 is electrically connected to the second electrode 12 in the MEA M1. The second discharge gas having further enhanced the D / H composition ratio in the first discharge gas is discharged as final output gas from the anode side gas chamber 31 of the MEA M2.SELECTED DRAWING: Figure 10

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.

Methods and systems directed to the separation of a heavy hydrogen isotope, e.g., tritium, from an aqueous stream are described. The methods and systems incorporate a separation media that includes a proton conducting ceramic that at low temperatures preferentially adsorbs heavy hydrogen isotopes and at high temperature preferentially adsorbs lighter heavy hydrogen isotopes. The methods can be temperature controlled to sequentially purify a contaminated stream and regenerate the separation media. The separation media can be free of traditional hydrogen isotope exchange catalyst materials.

The invention discloses a fusion reactor discharged ash gas treatment device, and belongs to the technical field of fusion reactors. The fusion reactor discharged ash gas treatment device comprises a shell forming a vacuum chamber; the gas supply part is used for inputting ash discharge gas into the vacuum chamber; the inductively coupled plasma generating device is used for enabling the discharged ash gas input into the vacuum chamber to generate plasma; the hydrogen selective membrane is arranged in the vacuum chamber and divides the vacuum chamber into a first cavity and a second cavity, the inductively coupled plasma generating device is at least partially located in the first cavity, and deuterium ions and tritium ions enter the second cavity through the hydrogen selective membrane and are combined to form deuterium and tritium gas; the bias power supply is electrically connected with the hydrogen selection membrane and is used for applying bias voltage with negative potential; the first discharge part is communicated with the first cavity; and the second discharge part is communicated with the second cavity. The deuterium and tritium gas treatment device not only is compact in structure and simple and convenient to operate, but also can reduce the retention volume and energy consumption of deuterium and tritium gas, and improves the operation reliability.

The invention provides a system and a method for extracting lithium from seawater and coupling to prepare deuterium gas. The system for extracting lithium from seawater and coupling to prepare deuterium gas comprises a desalination treatment part, an adsorption part, a concentration part, a filtering part and an evaporation electrolysis part which are sequentially connected in series. The desalting treatment part can be used for desalting seawater to produce strong brine; the adsorption part can adsorb and desorb strong brine to produce lithium-rich water. And the concentration part can be used for concentrating the lithium-rich water. And the filtering part can filter the lithium-rich water. The evaporation electrolysis part can evaporate the lithium-rich water to produce lithium ion crystals and crude heavy water, and then electrolyze the crude heavy water to obtain deuterium gas. The output end and the input end of the desalting treatment part are connected to enable strong brine to flow back, and the desalting treatment part is also connected with the backwashing water input end of the filtering part to enable the strong brine to backwash the filtering part. The backwashing water output end of the filtering part is connected with the input end of the desalting treatment part, so that backwashing water flows back. The utilization efficiency is improved, and the resource consumption is reduced.

The invention discloses a hydrogen isotope catalytic exchange catalyst and a preparation method thereof, the catalyst takes platinum as an active center and Ti3C2Tx as a carrier to enable platinum particles to be highly dispersed, so that the activity of platinum is improved, and meanwhile, Ti3C2Tx is a two-dimensional material to eliminate the influence of internal diffusion and capillary condensation of water on platinum. The prepared catalyst has the advantages of being high in catalytic exchange efficiency, good in stability, small in platinum consumption and the like, the catalytic exchange efficiency can reach 90% at the temperature of 40 DEG C, and the preparation method of the catalyst is simple and beneficial to large-scale production.

A process for the preparation of a saturated or ethylenically unsaturated aliphatic or cycloaliphatic compound comprising the following steps: (a) providing hydrogen with a molar share of deuterium ≤ 100 ppm, based on the total hydrogen content, by electrolysis of water using electrical power generated at least in part from non-fossil energy, (b) at least partially hydrogenating an ethylenically unsaturated compound to form the corresponding saturated compound, or at least partially hydrogenating an acetylenically unsaturated compound to form the corresponding saturated or ethylenically unsaturated compound

Methods and systems directed to the separation of tritium from an aqueous stream are described. The separation method is a multistage method that includes a purification stage during which tritium of a tritium-contaminated aqueous stream is adsorbed onto a cooled and wet separation phase, a regeneration stage during which the adsorbed tritium is exchanged with hydrogen in a gaseous stream to regenerate the separation phase and provide a gaseous stream with a high tritium concentration, and a third stage during which the tritium of the gaseous stream is separated from the gaseous stream as a gaseous tritium product.

A process for the preparation of amines comprising the following steps: (a) providing hydrogen with a molar share of deuterium ≤ 100 ppm, preferably in the range of from 10 to 95 ppm, more preferably in the range of from 15 to 90 ppm, most preferably in the range of from 20 to 80 ppm, especially in the range of from 30 to 75 ppm, based on the total hydrogen content, by electrolysis of water using electrical power generated at least in part from non-fossil energy, (b) reacting the hydrogen from step (a) with a nitrile compound or hydrogen cyanide (I)         R-CN     (I) to form the corresponding primary amine (II), secondary amine (III) and / or tertiary amine IV)         RCH2-NH2     (II),         (RCH2)2NH     (III)         (RCH2)3N     (IV) or mixture thereof.

An apparatus and method for integrated tritium extraction and recovery in a fusion power system includes combining-in a tritium extraction unit-a fluid tritium breeding composition with a second fluid to generate a combined fluid undergoing two phase flow, and extracting tritium from the breeding composition in the two-phase flow by simultaneous processes of permeation across a solid membrane and tritium transfer onto the second fluid (i.e., gas-liquid or liquid-liquid contacting).

A process for the preparation of amines comprising the following steps: (a) providing hydrogen with a molar share of deuterium ≤ 100 ppm, based on the total hydrogen content, by electrolysis of water using electrical power generated at least in part from non-fossil energy, (b) reacting the hydrogen from step (a) with nitrogen to form ammonia, (c) reacting the ammonia from step (b) with an alcohol R-OH in the presence of hydrogen from step (a) to form the corresponding primary, secondary and / or tertiary amines R-NH2, R2NH and / or R3N.