81 results about "Xenon" patented technology

The invention relates to an air suction type cusped field electric propulsion system with multiple working medium supply modes and a supply method. The invention relates to the technical field of air suction type electric propulsion systems. The system comprises an electric thruster and collection device module, a microwave cathode module, a xenon storage and supply module and a control and energy supply module. According to the air-breathing cusped field electric propulsion system with the multiple working medium supply modes, the adaptive capacity of the electric thruster under the complex working condition is improved through the xenon working medium carried by the air-breathing cusped field electric propulsion system while the ultra-low orbit rarefied atmospheric environment is fully utilized. In addition to an ultra-low rail air-breathing type electric propulsion task, the xenon working medium carried by the ultra-low rail air-breathing type electric propulsion device can enable the ultra-low rail air-breathing type electric propulsion device to give consideration to a higher rail range, and a traditional xenon electric propulsion rail interval and an ultra-low rail space of 150 km or above are covered.

The application provides a device for coupling xenon isotope separation and neon-helium purification separation and a use method thereof. Based on various non-low-temperature gas separation technologies, through multi-stage module cooperation, high-efficiency enrichment of xenon isotope raw material gas under non-low-temperature conditions and purification and purification of air separation crude neon-helium gas are coupled, including thermal coupling and intermediate material coupling. The crude neon-helium gas produced in the process is fully utilized, the energy consumption and operation complexity are significantly reduced, and the development advantage can be further improved.

This invention provides a method, apparatus, device, and medium for correcting control rod calibration curves. The correction method includes: acquiring a reference temperature curve during a load reduction period; correcting the reference temperature curve based on the negative reactivity introduced by xenon to generate a xenon correction curve; calculating an overheat correction curve based on a set balance coefficient, a primary loop completely untracked curve, and the xenon correction curve; calculating the power data in the overheat correction curve and its corresponding overheat correction power data based on the overheat correction curve and the reference temperature curve, and generating an overheat correction parameter set; and correcting the control rod calibration curve based on the overheat correction parameter set to generate a corrected control rod calibration curve. The method, apparatus, device, and medium provided by this invention can correct control rod calibration curves to adapt to different generating units.

The utility model relates to the technical field of gas production equipment, in particular to full-automatic ultra-pure helium and xenon gas purification equipment, when the full-automatic ultra-pure helium and xenon gas purification equipment is used, a catalyst is respectively arranged in each group of lower tank bodies, and a worker operates gas to enter the first group of lower tank bodies to carry out purification operation through the catalyst; when the catalyst in the first group of lower tank body needs to be replaced, the gas can be continuously purified while the catalyst is replaced, so that the processing efficiency is improved; comprising a supporting seat, lower tank bodies, upper tank bodies and supporting legs, the supporting legs are arranged at the bottom end of the supporting seat, two groups of lower tank bodies are fixedly mounted on the supporting seat, one group of upper tank bodies is detachably arranged at the top end of each group of lower tank bodies, the device further comprises locking assemblies, an air inlet assembly and an air exhaust assembly, and the lower tank bodies and the upper tank bodies are connected through a plurality of groups of locking assemblies. The output ends of the two groups of lower tank bodies are respectively communicated with the exhaust assembly, and the input ends of the two groups of upper tank bodies are respectively communicated with the output end of the air inlet assembly.

The present invention discloses a quantitative evaluation method of in vivo molecular probes based on xenon / phosphorus multi-nuclear magnetic resonance, which obtains the corresponding curve between the pH value of the molecular probe saturated solution and the molecular probe saturation concentration and 129 Sensitivity distribution diagram of the Xe transceiver integrated coil; obtain the hydrogen proton magnetic resonance structure image of the test area of ​​the test object; obtain the 3D 31 P chemical shift imaging data, to obtain molecular probe 129 Xe magnetic resonance signal distribution image; obtain pH value distribution image of the detection object to be tested area; obtain molecular probe concentration distribution image in the detection object to be tested area; calculate the molecular probe position coordinates of the detection object to be tested area and the molecular probe concentration distribution image; calculate the molecular probe position coordinates of the detection object to be tested area and the molecular probe concentration distribution image; calculate the molecular probe position coordinates of the detection object to be tested area and the molecular probe concentration distribution image; calculate the molecular probe concentration distribution image ... 129 The present invention can realize the concentration of molecular probes and the molecular probes that are difficult to detect in vivo without damage. 129 Quantitative measurement of parameters such as Xe apparent binding rate.

The utility model relates to a remote xenon control system, which comprises a gas storage module, a pressure regulation module, a pressure control module, a flow control module and a remote control terminal, wherein the pressure regulation module is used for regulating the pressure of the xenon, flowing out of the gas storage module, in the pipeline, meanwhile, the flow control module is arranged after the pressure of the xenon in the pipeline is stable, and the actual flow of the xenon in the pipeline is regulated in real time according to a given set value, so that the actual flow is consistent with the set flow; and the remote control terminal controls the actions of the pressure control module and the flow control module.

The invention provides a xenon bottle bearing hoop fixing structure which comprises hoop supports, a hoop belt, a tightening device and a punching rubber pad, the radial displacement of a xenon bottle is limited through the three hoop supports, the hoop belt penetrates through the hoop supports and is bound with a gas bottle body, all the supports form a whole, and all radial bidirectional constraints are indirectly generated. The three hoop supports are used for providing radial support for the gas cylinder from three directions, meanwhile, a flange installation face perpendicular to the gas cylinder is obtained, the hoop belts are used for binding the three hoop supports and the gas cylinder to form a whole, one-way support in the three directions is converted into two-way constraint in all the directions, and the perforated rubber pad serves as a compensation device for expansion of the gas cylinder. And the balance of support and compensation is achieved through different punching structure designs. The invention provides a high-reliability and high-bearing-capacity xenon cylinder fixing scheme, and the problem that radial constraint is insufficient when a large-loading-capacity xenon cylinder of a spacecraft is installed is solved.

This application relates to the field of quantum nondestructive testing technology, and discloses a quantum detection device and a xenon atom-based eddy current detection method. The quantum detection device includes an interconnected eddy current probe and a quantum measurement device. The quantum measurement device includes a xenon atom gas chamber for measuring the magnetic field strength of a target eddy current magnetic field. It acquires the target eddy current magnetic field of the target object, measures the magnetic field strength of the target eddy current magnetic field, and obtains the magnetic field strength distribution along the surface of the target object. Based on the magnetic field strength distribution, it detects thickness changes in the target object to obtain the weak point detection result. Its beneficial effect is that by measuring the eddy current magnetic field generated by the target object through a xenon atom gas chamber, it effectively utilizes the characteristics of xenon atoms—long coherence time and extremely low resonance frequency—thereby maintaining high sensitivity to capture weak magnetic fields at extremely low frequencies and obtaining a detection penetration depth far exceeding that of traditional sensors, achieving high-precision nondestructive testing of minute thickness differences inside the target object.

The invention discloses a preparation method of homogeneous high-purity scandium-aluminum alloy powder, and belongs to the technical field of alloy material preparation. The method comprises the following steps that metal scandium and aluminum metal ingots are prepared according to the atomic ratio of scandium to aluminum being 1: 3-3: 1 and then placed into a smelting furnace, and smelting and heat preservation are conducted under the argon atmosphere; the alloy solution is poured into a rotary water-cooling copper roller with the linear speed of 2-5 m / s to achieve rapid hardening, and a scandium-aluminum alloy sheet is prepared; the scandium-aluminum alloy sheet is activated and then subjected to hydrogenation-dehydrogenation treatment; and finally, xenon is used as working gas for airflow pulverization, and scandium-aluminum alloy powder of 10-75 microns is obtained through airflow separation. According to the method, the polycrystalline alloy sheet with fine grains is prepared through rapid hardening, hydrogen decrepitation is promoted through the grain boundary, pollution of a ball milling medium is avoided, the problems that in the prior art, alloy powder is low in purity, uneven in grain size and low in crushing yield are solved, and the prepared alloy powder is homogeneous, high in purity and suitable for preparation of high-end products such as target materials.

The invention relates to an atomic gas chamber and a preparation method thereof. The preparation method of the atomic gas chamber comprises the following steps: providing an atomic gas chamber glass bulb; rubidium steam is filled in the atomic gas chamber glass bulb; the atomic gas chamber glass bulb is filled with mixed gas; wherein the mixed gas comprises xenon 129, xenon 131, hydrogen and a buffer gas; the voltage division ratio of the xenon 129 to the xenon 131 is (1: 4)-(1: 9); carrying out heat preservation treatment on the atomic gas chamber glass bulb, and reacting rubidium steam with hydrogen to generate a rubidium hydride film layer; and the rubidium hydride film layer covers the inner wall of the atomic gas chamber glass bulb. According to the preparation method of the atomic gas chamber, provided by the invention, the atomic spin relaxation time of xenon 129 and xenon 131 can be prolonged, the relaxation performance of two isotopes can be balanced, the performance of the atomic gas chamber is further improved, and the requirements of application scenes such as a quantum inertia instrument on the atomic spin stability of the atomic gas chamber are met.

The invention discloses a reactor core power control method which comprises the following steps: during base load operation, inserting and / or lifting a T rod group for temperature regulation and compensation of reactor core reactivity change into and / or from a reactor core, and compensating reactor core temperature change caused by excess reactivity and burnup effect; during operation in a load tracking mode, the effect caused by power change and the coolant temperature change caused by xenon poison change effect are compensated by the T rod group, and the average temperature of the coolant is kept in an operation interval. According to the reactor core power control method disclosed by the invention, automatic control of the reactor core power and temperature in the reactor core operation process is realized only through insertion / lifting of the T rod group; the method is suitable for the reactor core with low linear power density, and under the condition of no axial power distribution control requirement, the reactor core axial power distribution under various normal operation and accident working conditions can still ensure the safety of the reactor core.

The invention is applicable to the technical field of nuclear reactors, and provides a xenon reactivity calculation method, device, equipment and product for a nuclear reactor. The method comprises the following steps: acquiring current set parameters for processing furnace charge in the nuclear reactor and multiple groups of optimal xenon information corresponding to the nuclear reactor; the furnace charge in the nuclear reactor generates xenon in the fission reaction process; according to the multiple sets of optimal xenon information, target xenon parameters of the nuclear reactor processed under the current furnace charge circulation parameters and the current furnace charge burnup parameters are determined; the xenon reactivity generated by the charge in the nuclear reactor is calculated based on the target xenon parameter. According to multiple groups of optimal xenon information corresponding to the nuclear reactor, the target xenon parameters processed by the nuclear reactor under the current furnace charge circulation parameters and the current furnace charge burnup parameters are determined, and the xenon reactivity is calculated according to the target xenon parameters, so that the accuracy of the xenon reactivity is improved; and an effective reference basis is provided for an operator to manage the nuclear reactor.

The invention provides modified activated carbon for xenon adsorption. The BET (Brunauer, Emmett and Teller) specific surface area of the modified activated carbon is 1000m / g to 1050m / g. The modified activated carbon provided by the invention has improved adsorption performance on xenon.

The application discloses a multi-mode enrichment analysis device and process capable of detecting xenon background in air, which comprises a gas taking and enrichment unit, a pressurized adsorption, vacuum desorption and reverse desorption purification and concentration unit connected with each other through a gas flow pipeline and a refrigerator for realizing shallow low temperature. The application controls the adsorption temperature of the refrigerator to be-28 DEG C to 18 DEG C, raises the tail pressure of each xenon separation column, and increases the dynamic adsorption coefficient of each xenon separation column from 0.43 L / g under normal temperature and pressure to 1.2-3.4 L / g, thereby improving the adsorption efficiency and reducing the adsorbent loading amount of each xenon separation column under the determined gas volume. Through vacuum desorption and reverse desorption, the carrier gas volume of complete desorption can be reduced from 8-20 times the desorption volume to 3-5 times, thereby improving the desorption efficiency. The column filler loading surplus can be increased from about 30% to 50-300%, thereby greatly improving the stability and reliability of the device, and realizing self-adaption of the filler usage amount to the gas taking amount, which can meet the needs of high-sensitivity large-volume sampling monitoring and sensitive and rapid sampling monitoring.

The invention discloses a nuclear reactor core power capability verification method and device, and the method comprises the steps: obtaining first xenon atomic nucleus density distribution data of a reactor core according to a target reactor core working condition point corresponding to a typical burnup condition for any typical burnup condition of a plurality of typical burnup conditions of the reactor core; performing order reduction processing on the first xenon atomic nucleus density distribution data to obtain a plurality of low-order primary functions corresponding to the typical burnup condition and a target range of expansion coefficients corresponding to the plurality of low-order primary functions; obtaining second xenon atomic nucleus density distribution data corresponding to the typical burnup condition according to a plurality of recovery expansion coefficients corresponding to the typical burnup condition and a plurality of low-order basis functions; determining reactor core power distribution data corresponding to the typical burnup condition according to the second xenon atomic nucleus density distribution data; and performing power limit value verification on the reactor core power distribution data corresponding to each typical burnup condition to obtain a power capability verification result. According to the invention, the power capability verification calculation efficiency can be improved.

The invention discloses a reactor core control method which comprises the following steps: during base load operation, inserting and / or lifting a T rod group for temperature regulation and compensation of reactor core reactivity change into and / or from a reactor core, and compensating reactor core temperature change caused by excess reactivity and burnup effect; the P rod group for regulating and controlling the power of the reactor core keeps still along with the power; and when the load tracking mode runs, the effect caused by power change is compensated by the P rod group, the coolant temperature change caused by xenon poison change effect is compensated by the T rod group, and the average temperature of the coolant is kept in the running interval. According to the reactor core control method, reactor core power and temperature control is achieved through the P rod set and the T rod set, meanwhile, reactor core hot spot factors are reduced, the operation allowance and the safety allowance of the reactor core are ensured, and then the unit operation economical efficiency is improved.

The present application relates to the technical field of xenon recovery control, and particularly relates to a xenon recovery and purification device for anesthetic mixed gas and an intelligent control system. The device comprises a data acquisition module for acquiring gas state data of each molecular sieve tower in real time; a processing control unit for determining a xenon migration index based on the pressure in the tower and the xenon migration amount of each molecular sieve tower at any time; determining a switching urgency according to the gas concentration change characteristics and the feed flow rate fluctuation characteristics; generating a comprehensive switching degree in combination with the xenon migration index and the switching urgency; monitoring the change trend of the comprehensive switching degree over time in real time to determine a change rate; determining the best switching time when the change rate is first lower than a preset convergence threshold; and a switching module for triggering a double molecular sieve tower mode switching at the best switching time, thereby significantly improving the xenon purification efficiency of the device.

The invention relates to the technical field of xenon recovery control, in particular to a xenon recovery and purification device for anesthesia mixed gas and an intelligent control system. The device comprises a data acquisition module used for acquiring gas state data of each molecular sieve tower in real time; the processing control unit is used for processing the xenon migration volume of each molecular sieve tower at any moment based on the pressure in the tower; determining a xenon migration index; the switching urgency degree is determined according to the gas concentration change characteristics and the feeding flow velocity fluctuation characteristics; generating a comprehensive switching degree in combination with the xenon migration index and the switching urgency degree; the change trend of the comprehensive switching degree along with time is monitored in real time, and the change rate is determined; when the change rate is lower than a preset convergence threshold value for the first time, determining an optimal switching moment; and the switching module is used for triggering mode switching of the double molecular sieve towers at the optimal switching moment, so that the xenon purification efficiency of the device is remarkably improved.

Embodiments of the present disclosure generally relate to methods of plasma curing a dielectric material layer formed on a substrate. More specifically, the methods disclosed herein utilize a xenon (Xe) containing gas to generate a plasma that allows for greater dielectric compositional modulation. In some embodiments, a method of curing a substrate includes depositing a dielectric film onto a substrate to form a dielectric layer on a surface of a substrate, and performing a plasma cure operation on the formed dielectric layer. The plasma cure operation includes generating a plasma over a surface of the formed dielectric layer by delivering a RF power to a plasma process gas. The plasma process gas include Xe and H2.

This invention relates to a multi-propellant supply mode air-breathing tangential field electric propulsion system and its supply method. The invention pertains to the technical field of air-breathing electric propulsion systems. The system includes: an electric thruster and collection device module, a microwave cathode module, a xenon gas storage and supply module, and a control and energy supply module. The multi-propellant supply mode air-breathing tangential field electric propulsion system provided by this invention, in addition to fully utilizing the thin atmosphere of the ultra-low Earth orbit (ULE), enhances the adaptability of the electric thruster under complex operating conditions by utilizing its own xenon propellant. Beyond ULE air-breathing electric propulsion missions, the xenon propellant it carries enables it to operate over a wider orbital range, covering the orbital range of traditional xenon electric propulsion and ULE space above 150 km.

The application discloses a coincidence detection device for radioactivity measurement, comprising a frame, a detector arranged on the frame, and an air inlet and outlet interface; the frame is internally provided with a gas measurement chamber; the frame is a semi-regular polyhedron comprising a triangular face and a square face, and the detector is arranged on the square face; and the detector is a cadmium zinc telluride detector. The detection device is especially suitable for radioactivity measurement of radioactive xenon, solves the defects of a high-purity germanium gamma spectrometer and a NaI+plastic scintillator beta-gamma coincidence detector, such as large volume, large weight, difficult maintenance, and difficulty in realizing portability and on-site measurement, and can achieve a lower detection limit, has higher measurement accuracy than a NaI detector, adopts a semi-regular polyhedral design for the detector shape, guarantees the spatial symmetry of the detectors, obtains a larger 4pi coverage rate of the detector, increases the volume of the measurement chamber, reduces the requirement for air separation and concentration, and solves the problem of the limited measurement chamber of a traditional beta-gamma coincidence detector.

This invention belongs to the technical field of reactor moderator temperature coefficient measurement methods under power conditions, specifically relating to a method for measuring the reactor moderator temperature coefficient under power conditions. It includes the following steps: Step 1: Confirm or create a reactor xenon imbalance state; Step 2: Set the control rods to manual mode, maintaining constant power and boron concentration; Step 3: Collect reactor power and moderator temperature data to measure the moderator temperature coefficient; Step 4: Calculate xenon toxicity based on power; Step 5: Obtain the Doppler temperature coefficient α under this state according to the design. dop Step 6: Calculate the overall temperature coefficient α ttc The overall temperature coefficient α ttc It equals the negative of the reciprocal of the slope of the rate at which the average temperature of the moderator changes with xenon toxicity; Step 7: Based on α mod =α ttc -α dop Calculation of the temperature coefficient of a moderator. This invention provides a method for measuring the temperature coefficient of a moderator using changes in xenon toxicity. The xenon toxicity calculation is reliable, the measurement time is short, and the measurement error of the temperature coefficient of the moderator can be reduced.

The invention relates to the technical field of intense pulsed light therapeutic apparatuses, and discloses a preparation method of a rare earth flash lamp tube for an intense pulsed light therapeutic apparatus, and the method comprises the steps: heating an organic metal rare earth precursor to form steam, carrying out gas-phase mixing on the steam, xenon and sacrificial reaction gas, filling a lamp tube with the mixed gas, and sealing the lamp tube; and then an initial pulse program is applied to the sealed lamp tube. The procedure comprises a low-temperature pyrolysis and purification stage and a high-temperature activation and electrode surface passivation stage. In the low-temperature stage, the precursor is decomposed through low-energy pulses, and the sacrificial gas reacts with the carbon-containing by-product; in the high-temperature stage, high-energy pulses are used for activating rare earth elements, and part of the rare earth elements are promoted to form passivation layers on the surfaces of the electrodes. Atomic-scale uniform distribution of rare earth elements is achieved through gas phase doping, a solid carbon source is removed through an in-situ chemical reaction, electrode sputtering is inhibited through electrode surface passivation, and therefore the spectrum output stability and the inner wall cleanliness of the flash lamp tube are remarkably improved, and the working life of the flash lamp tube is remarkably prolonged.

Test chamber (10) for conditioning air, comprising a temperature-insulated test chamber (12) that can be closed off from the environment for receiving test material and a temperature control device (11) for temperature control of the test chamber, wherein a temperature in a temperature range of -80 °C to +180 °C can be established within the test chamber by means of the temperature control device, wherein the temperature control device comprises a cooling device (16) with a cooling circuit (17) with a refrigerant, a heat exchanger (18) arranged in the test chamber, a compressor (19), a condenser (20) and an expansion element (21), wherein the temperature control device (11) comprises a heating device (23) with a heater and a further heat exchanger (22), characterized in that the refrigerant is a nearly azeotropic refrigerant mixture consisting of a mass fraction of carbon dioxide and a mass fraction of at least one of the components ethene, hexafluoroethane, monofluoroethane, 1.1 Difluoroethene, fluoromethane and / or propane and / or xenon, wherein the refrigerant has a relative CO2 equivalent, based on 20 years, of < 2500, wherein a first bypass (43) with at least one further throttling element (44) is formed in the cooling circuit (17), wherein the first bypass (43) bridges the compressor (19) downstream of the compressor (19) and upstream of the condenser (20) in the direction of flow, wherein a pressure difference between a high-pressure side (26) and a low-pressure side (27) of the cooling circuit (17) can be equalized via the further throttling element (44).

This disclosure relates to a method (100) for assisting in the stabilization of a nuclear reactor, the method being implemented by computer and comprising the steps of: receiving (101) input data representative of the position of the reactor's neutralizing control rods; from the input data, generating (102): a simulated evolution of an iodine parameter indicative of an axial imbalance of the quantity of iodine in the nuclear reactor, a simulated evolution of a xenon parameter indicative of an axial imbalance of the quantity of xenon in the nuclear reactor, and a simulated evolution of a power parameter indicative of an axial imbalance of the thermal power generated in the nuclear reactor; generating (103) a graph superimposing the simulated evolution of the iodine parameter, the simulated evolution of the xenon parameter, and the simulated evolution of the power parameter. (Short figure: Fig. 3)

The application relates to the technical field of nuclide detection, and provides a detection device and a detection system. The detection device comprises multiple xenon adsorption boxes and a sample changing assembly. The multiple xenon adsorption boxes are arranged in the sample changing assembly. The sample changing assembly has a sampling station, a measuring station and an activation station. The sample changing assembly is used for driving the multiple xenon adsorption boxes to move, so that the sampling station, the measuring station and the activation station have one xenon adsorption box respectively. The detection device provided by the embodiment of the application can realize uninterrupted and continuous measurement of radioactive xenon, shorten a measurement time period and improve the measurement efficiency of radioactive xenon.

This invention specifically relates to a method for correcting the critical boron concentration under full power conditions. Based on a three-dimensional reactive equilibrium equation and considering the influence of temperature deviation on the Doppler effect, the critical boron concentration under full power conditions is: where CB ref This represents the critical boron concentration at full power; CB m ρ represents the actual boron concentration under the measured conditions. xem Indicates the equilibrium xenon poisoning under measurement conditions; ρ xeref This represents the balanced xenon poisoning at full power; ρ rccam Indicates the reactivity introduced by the control rod under measurement conditions; pr m Indicates the actual power under the measured conditions; HFP represents full power; α pc α represents the average of the sum of the power coefficients under the measured state and the full-power state; b T represents the average of the sum of the differential boron values ​​under the measured state and the full-power state; avgm T represents the average temperature of the moderator under the measured conditions. ref (pr m ) represents the moderator reference temperature under measurement conditions; α ttcm This represents the total temperature coefficient under the measurement conditions. The invention also relates to computer equipment and a computer-readable storage medium, outlining the steps for implementing the above-described method for correcting the critical boron concentration under full power conditions. Based on a three-dimensional reactive equilibrium equation, and considering the influence of temperature deviation on the Doppler effect, this invention achieves accurate correction of the critical boron concentration under full power conditions when nuclear power units increasingly participate in peak shaving.

Passive reactivity control technologies that enable reactivity control of a nuclear thermal propulsion (NTP) system with little to no active mechanical movement of circumferential control drums. By minimizing or eliminating the need for mechanical movement of the circumferential control drums during an NTP burn, the reactivity control technologies simplify controlling an NTP reactor and increase the overall performance of the NTP system. The reactivity control technologies mitigate and counteract the effects of xenon, the dominant fission product contributing to reactivity transients. Examples of reactivity control technologies include, employing burnable neutron poisons, tuning hydrogen pressure, adjusting wait time between burn cycles or merging burn cycles, and enhancement of temperature feedback mechanisms. The reactivity control technologies are applicable to low-enriched uranium NTP systems, including graphite composite fueled and tungsten ceramic and metal matrix (CERMET), or any moderated NTP system, such as highly-enriched uranium graphite composite NTP systems.

The invention provides a xenon three-phase point reproduction method and system suitable for a long rod standard platinum resistance thermometer, and the system comprises a xenon three-phase point reproduction device, a liquid nitrogen Dewar, and a temperature controller. The xenon three-phase point reproduction device is positioned in the cavity of the liquid nitrogen Dewar; the xenon three-phase point reproduction device comprises a thermometer trap, a xenon three-phase point container in which a xenon sample is arranged, a radiation screen, a heating layer positioned on the outer wall of the radiation screen, and a vacuum bin; wherein part of the thermometer trap is located in the xenon three-phase point container, the xenon three-phase point container is located in a cavity of the radiation screen, and the radiation screen is located in a cavity of the vacuum bin; the rest thermometer trap sequentially passes through the top of the radiation screen, the top of the vacuum bin and the top of the liquid nitrogen Dewar flask from the top of the xenon triphase point container to extend to the outside of the liquid nitrogen Dewar flask; helium is filled into the vacuum bin, and liquid nitrogen is injected into the liquid nitrogen Dewar; and the xenon sample is solidified and melted until a solid-liquid interface is formed around the thermometer well, and then xenon three-phase point internal melting is completed.

The invention discloses a device and process for adsorbing and enriching xenon in nuclear waste gas in a pressure-variable and temperature-variable vacuum mode, and belongs to the field of engineered xenon recovery. The device comprises a pretreatment module, a xenon enrichment module, a xenon storage module and a program control valve, the pretreatment module comprises a raw material gas compressor, one end of the raw material gas compressor is connected with nuclear fuel waste gas, and the other end of the raw material gas compressor is connected with the program control valve; the other end of the pretreatment module is connected to a first high-pressure adsorption tower and a first low-pressure regeneration tower which alternately operate through a feed gas heat exchanger, and an outlet of the pretreatment module is connected to a xenon enrichment module; the xenon enrichment module comprises a buffer tank, an outlet of the pretreatment module is connected to the buffer tank, an outlet of the buffer tank is divided into two paths, one path is connected to the top of a second high-pressure adsorption tower and the top of a second low-pressure regeneration tower, the other path is connected to the bottoms of a second high-pressure adsorption tower and a second low-pressure regeneration tower which alternately operate through a pretreatment gas heat exchanger, and an outlet of the xenon enrichment module is connected to a xenon storage module; the program control valve comprises a plurality of valves connected with the pipeline.