80 results about "Radioactive gas" patented technology

The invention discloses a radioactive air filtering device, and relates to the technical field of radioactive gas treatment. Comprising a particle impurity removal mechanism, a spraying mechanism and an adsorption mechanism, the particle impurity removal mechanism comprises an impurity removal barrel, and an efficient air filter screen is rotationally arranged in the impurity removal barrel; the spraying mechanism comprises a washing tank, a spraying pipe is rotatably arranged in the washing tank, a plurality of spraying heads are fixedly arranged on the lower surface of the spraying pipe, a rotary movable pipe is rotatably arranged on the upper surface of the washing tank, and the bottom end of the rotary movable pipe extends into the washing tank and is fixedly connected with the upper surface of the spraying pipe. By arranging the particle impurity removal mechanism, radioactive air can be primarily filtered through a cylindrical efficient air filter screen in an impurity removal barrel, large-particle dust and impurities in the radioactive air are effectively removed, and meanwhile radioactive aerosol in the radioactive air can be captured and adsorbed through the efficient air filter screen; and preliminary filtration of radioactive gas is realized.

The invention discloses radioactive gas separation and purification equipment, a radioactive gas separation and purification method, a radioactive gas separation and purification medium and radioactive gas separation and purification equipment, and relates to the technical field of radioactive gas separation and purification. The radioactive gas separation and purification equipment comprises a first separation column, a second separation column, a carrier gas container, a quantitative structure, a chromatographic column, a detection assembly, a first control valve, a storage container, a temperature controller and a to-be-treated gas container. The carrier gas container is connected with the first control valve, and the to-be-treated gas container, the quantitative structure, the first control valve, the first separation column, the second separation column, the chromatographic column and the storage container are sequentially connected. The first separation column, the second separation column and the chromatographic column are all filled with stationary phases which are all used for purifying target substances in the to-be-treated gas based on different adsorption rates of the stationary phases relative to different substances. Therefore, due to the arrangement of the first separation column, the second separation column and other structures, large-volume ambient air or gaseous effluent can be purified, and subsequent radioactive substance concentration measurement is facilitated.

The invention provides a radioactive source for a thickness measuring device, and the radioactive source comprises a box body part which is provided with a containing cavity and an exit window, and the containing cavity is used for containing beta radioactive gas; the collimation part is arranged on the box body part, a plurality of emergent channels which are arranged at intervals are formed, the emergent channels are conducted in the first direction, and the emergent window covers one end of each emergent channel; the electric field generating part is arranged in the box body part and is used for forming an electric field in the accommodating cavity; the direction of the electric field is parallel to the first direction, and the electric field points to the interior of the containing cavity from the emergent window. According to the radioactive source, beta rays emitted to the emergent window in the accommodating cavity or beta rays emitted through the emergent window can be screened by utilizing the collimating part, so that part of beta rays with high consistency with the first direction can be emitted out of the box body part through the emergent channel and the emergent window so as to participate in thickness measurement of an object to be measured; therefore, the collimation of the emitted beta ray is improved, and the measurement precision of the thickness measurement device is improved.

The protective transportation device for the medical radiopharmaceuticals comprises a protective barrel, a protective cover and a plurality of adsorption assemblies arranged in the protective barrel, storage grooves are formed among the adsorption assemblies, the adsorption assemblies are distributed in the circumferential direction of an inner cavity of the protective barrel at equal angles, and the radial sections of the adsorption assemblies are each of a 90-degree fan-shaped structure; each adsorption assembly comprises a plurality of splicing frames, every two adjacent splicing frames are tightly attached, circulating holes are formed in the circumferential outer walls of the splicing frames, the multiple adsorption assemblies distributed in the circumferential direction at equal angles are arranged in the protection barrel, the radial section of each adsorption assembly is of a 90-degree fan-shaped structure, and the multiple adsorption assemblies are formed by stacking the multiple splicing frames; the circulation holes of the adjacent splicing frames are formed in a staggered mode to form a continuous snake-shaped airflow channel, the structure remarkably prolongs the escape path of radioactive gas, the gas is forced to undergo multiple times of steering and diffusion resistance when passing through the multiple adsorption layers, and therefore the leakage risk is effectively reduced.

The utility model provides a gas purification system of a reactor. The gas purification system comprises a purification pipeline, and an inert gas adsorber, an iodine adsorber, a polonium processor, a filter and a radioactivity analyzer which are arranged on the purification pipeline. And the inert gas adsorber is used for removing inert gas in the mixed gas. The iodine adsorber is used for removing iodine in the mixed gas. The polonium processor is used for removing polonium in the mixed gas. And the filter is used for removing small particles in the mixed gas. And the radioactivity analyzer is used for detecting the radioactivity of the mixed gas. According to the gas purification system, aiming at the characteristics of radioactive substances of the metal fast reactor, a four-stage purification treatment device is arranged to remove radioactive gas in the mixed gas, and in addition, a radioactivity analyzer is further arranged and used for detecting and judging whether the radioactivity in the gas meets the emission standard or not; and the problem of radioactive substance release caused by leakage of the containment is effectively avoided.

The present invention discloses a degassing device and method for on-line liquid scintillation, which relates to the field of radioactive nuclide measurement. The device includes a degassing tank, a screen hole adsorption layer and a diaphragm pump. The inner cavity of the degassing tank is divided into a first area and a second area. The degassing tank is externally connected with a liquid inlet pipe communicating with the first area, and the degassing tank is externally connected with a film pipe communicating with the second area. The film pipe is used to connect with a scintillation liquid storage tank; the screen hole adsorption layer is arranged in the second area, and the air extraction end of the diaphragm pump is connected to the outer wall of the degassing tank and communicates with the first area; the first area is a vacuum area, and the second area is a solution area; the method is realized by using this device. The degassing device and method for on-line liquid scintillation provided by the present invention not only have the advantages of on-line measurement, are safer and more efficient during the radioactive substance test process, but also the impurity removal stage is carried out in categories and in sequence, and the purpose of high-efficiency impurity removal can be achieved in a short time, especially suitable for the scenario of on-line measurement of radioactive gas impurities.

The embodiment of the invention is suitable for the technical field of nuclear power, and provides a ventilation system and a control method of the ventilation system, and the ventilation system and the control method are applied to an emergency resident area of a nuclear power plant. Different purification units are mounted in different areas of the emergency residence area; the purification units with different function types are used for filtering different radioactive substances; the radioactive substances comprise radioactive particles, radioactive aerosol and radioactive gas; each purification unit comprises an air inlet module, a purification module and an air exhaust module; the air inlet module is connected with the purification module and used for introducing air in the emergency residence area into the purification module; and the purification module is connected with the exhaust module and is used for filtering radioactive substances corresponding to the function type of the purification unit and exhausting the filtered air into the emergency resident area through the exhaust module. According to the ventilation system provided by the embodiment of the invention, the safety of the emergency resident area can be improved.

The invention provides a molten salt reactor radioactive gas removal device which comprises a main loop module, a gas injection module, a tail gas analysis and treatment module and an observation module, one end of the main loop module is connected with the gas injection module, the other end of the main loop module is connected with the tail gas analysis and treatment module, and the observation module is connected with the tail gas analysis and treatment module. The main loop module comprises a bubbler and a separator, the bubbler is filled with liquid for dissolving gas, and the observation module is arranged at a visual window on the side of a body of the bubbler and the separator; when the radioactive gas is removed, cavitation microbubbles and carrier gas microbubbles which are used for dissolving the radioactive gas are separated out by the bubbler, the cavitation microbubbles and the carrier gas microbubbles form a gas core by the separator, and the gas core is treated by the tail gas analysis and treatment module. According to the invention, deep dissolution and gas removal can be realized, the system sealing performance is good, the gas can be ensured not to leak, and the safety of operators and the environment is ensured.

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

To provide a radioactive substance removal device capable of enhancing efficiency of moisture removal as pretreatment of radioactive gas.SOLUTION: And a radioactive substance remover 3 that removes a radioactive substance from the gas from which moisture has been removed by the moisture remover 2, in which the moisture remover 2 has a flow path through which the gas flows, and removes moisture by cooling the gas in the flow path to frost moisture on a predetermined portion, and the flow path has a narrower flow path cross-sectional area or a shorter cooling wall surface distance on a downstream side than on an upstream side.SELECTED DRAWING: Figure 1

The invention discloses an application of a pure silicon molecular sieve in efficient trapping of trace krypton gas under a humid condition, the ZSM-11 pure silicon molecular sieve with MEL configuration is used as an adsorbent, efficient trapping of trace krypton gas in air is realized under a high-humidity environment, the molecular sieve has obvious Kr / N2 selectivity, and the molecular sieve can be used as an adsorbent for efficient trapping of trace krypton gas. The molecular sieve can effectively trap and separate 500 ppm krypton gas in air in a dynamic penetration experiment, and still can keep excellent separation performance even under the condition that the relative humidity reaches up to 72.6%, meanwhile, in the desorption process, enriched krypton gas with the concentration reaching up to 85% can be obtained through the method, and the method is suitable for industrial production. The method is suitable for the fields of nuclear facility waste gas treatment, radioactive gas monitoring and nuclear emergency response.

The embodiment of the invention relates to a radioactive gas measuring device, comprising: a chamber body, in which a gas chamber for accommodating gas to be measured is formed, and the chamber body is provided with a mounting port communicated with the gas chamber; the detector is arranged at the mounting opening, the detection surface of the detector faces the interior of the air chamber, and the detector blocks the mounting opening to form a sealing boundary of the air chamber; wherein the chamber body or the detector is provided with an air inlet channel and an air outlet channel which are communicated with the air chamber. The PIPS detector directly blocks the mounting port and forms a sealed boundary, so that the direct contact between the detection surface and the detected gas is realized, the attenuation of a window material to alpha particles or low-energy beta particles is eliminated, the measurement sensitivity is improved, and the limitation that the detector in the traditional measurement device needs to be placed in an independent sleeve or measured through a protection window is overcome; meanwhile, the detector serves as the top wall of the cavity body and is matched with the air inlet channel and the air outlet channel which are integrated on the cavity body or the detector, so that the whole device is more compact in structure.

The utility model relates to a high-sensitivity radioactive gas activity measuring device which comprises a set of double-beta plastic scintillator detector, two sets of gamma detectors, an anti-cosmic ray detector group and a digital coincidence circuit. The double-beta plastic scintillator detector and the gamma detectors are arranged in the lead shielding chamber, the double-beta plastic scintillator detector is arranged between the two gamma detectors, and mutual interference among radioactive gases in the double-beta plastic scintillator detector can be eliminated through coincidence and anticoincidence among four paths of signals; and the anti-cosmic ray detector group is used for shielding coincidence signals generated by cosmic rays in the double-beta plastic scintillator detector and the gamma detector. According to the utility model, a gamma detector original spectrum, an anti-cosmic ray gamma spectrum, a beta-gamma coincidence spectrum and an anti-cosmic ray beta-gamma coincidence spectrum, wherein the beta-gamma coincidence spectrum and the anti-cosmic ray beta-gamma coincidence spectrum are used for eliminating mutual influence among different radioactive gases. According to the utility model, synchronous measurement of different radioactive gases can be realized, and the detection sensitivity of the radioactive gases can be greatly improved.

The present invention belongs to the field of nuclear radiation protection technology and provides a radioactive gas detection device based on a silicon drift detector. The device comprises a silicon drift detector and a sampling chamber. The sampling chamber has a circular hole at the top. The silicon drift detector is mounted above the sampling chamber with a beryllium window facing the circular hole. The gas to be measured enters the sampling chamber through an inlet pipe, and the gas in the chamber flows out through an outlet pipe. The outlet pipe is arranged offset from the inlet pipe. A preamplifier circuit board and a signal processing board are mounted above the silicon drift detector via a fixed holder. The silicon drift detector, preamplifier circuit board, and signal processing board are disposed within a detector housing, which is fixedly connected to the sampling chamber. A connector is provided at the top of the detector housing. The device can simultaneously calculate radioactive activity and perform nuclide identification. The device uses simulated data and real X-ray data to calculate gamma background counts. The corresponding functions can be achieved using only one detector, greatly improving detector utilization.

The invention relates to the technical field of air purification devices in the nuclear field, and discloses an air purification device for emergency treatment of radioactive gas in a nuclear power plant, the air purification device comprises a base, a backflushing mechanism is arranged above the base, a bombardment mechanism is arranged above the base, the backflushing mechanism comprises a tower body, and the bottom surface of the tower body is fixedly connected with the upper surface of the base; an activated carbon bed layer is clamped in the tower body, a treatment box is fixedly mounted on the upper surface of the base, the end, close to the tower body, of the treatment box penetrates into the tower body, a filter screen is fixedly mounted on the inner wall of the treatment box, and an electrostatic dust collector is fixedly mounted on the inner wall of the treatment box. According to the air purification device for emergency treatment of the radioactive gas in the nuclear power station, the backflushing mechanism is arranged, nitrogen in the storage box is sprayed to the activated carbon bed layer through the air pump after passing through the conveying pipe and the spray head, and therefore cakes on the activated carbon bed layer are blown off through airflow; the problem that the purification efficiency of radioactive gas is reduced because a large number of cakes adhere to the activated carbon bed layer is avoided.

The invention discloses an ultrahigh pressure air valve component unit performance test device and method, and the device comprises an ultrahigh pressure compression closed circulation system which comprises an ultrahigh pressure air cylinder, a plunger and an ultrahigh pressure air valve test component, and ultrahigh pressure air enters an air cylinder compression cavity through an air inlet pipeline along an air inlet channel; ultrahigh-pressure gas in the gas cavity compression cavity is exhausted to the ultrahigh-pressure pressure relief device through an exhaust channel, the ultrahigh-pressure pressure relief device is connected to the gas inlet pipeline through a bypass pipeline, and a cyclotron is arranged on the gas inlet pipeline, prepares the ultrahigh-pressure gas into radioactive gas and introduces the radioactive gas into the ultrahigh-pressure cylinder; a scintillation detector array is arranged outside the ultrahigh-pressure cylinder, covers the whole ultrahigh-pressure cylinder and is used for capturing the flowing range of radioactive gas in the ultrahigh-pressure cylinder. The device has the functions of accurate ultrahigh-pressure gas loading, adjustable cycle frequency, working performance monitoring and the like, so that effective experimental means and technical guarantee are provided for localization of key parts.

The utility model provides a kind of safety shell ring corridor's ventilation system, the safety shell ring corridor's ventilation system includes the first exhaust system, second exhaust system and third exhaust system for gas flow of safety shell ring corridor and safety shell outside. Among them, first exhaust system is set in first fire compartment, second exhaust system is set in second fire compartment, and first fire compartment and second fire compartment are physically separated. By designing two independent and mutually redundant first exhaust system and second exhaust system, for accident condition, collect the gas leakage from inner layer safety shell to safety shell ring corridor and the gas flow in safety shell ring corridor from outer layer safety shell, to reduce the radioactive gas leakage amount in safety shell ring corridor as far as possible, ensure the working stability of entire ventilation system. While third exhaust system maintains the negative pressure in safety shell ring corridor not less than design reference under normal condition.

The invention discloses a radioactive gas source box assembly and a filling shielding method thereof. The radioactive gas source box assembly comprises a source box body which comprises a gas chamber and a breather pipe communicated with the gas chamber; the packaging cover is arranged above the gas chamber, the packaging cover is connected with the side, facing the ventilation pipe, of the gas chamber, and the ventilation pipe is located in the packaging cover; wherein the source box body and the packaging cover form an initial source box. The sealing and transporting reliability of the radioactive gas source can be guaranteed, the leakage of the radioactive gas source in the packaging process can be avoided through a filling shielding method, the health of workers is not affected, and the safety of the working environment is improved.

1. The name of the design product: source box. 2. The use of the design product: encapsulation container of radioactive gas. 3. The design points of the design product: in shape. 4. The picture or photo that best indicates the design points: perspective view 1.

This invention discloses a radioactive waste liquid sampling and measurement device and system, belonging to the field of waste liquid sampling and measurement technology. The invention includes a sealed chassis with a rotating top plate on top. A top frame and a gas storage bladder frame are located at the center of the top of the rotating top plate. A sampling column and a cap-removing cylinder are sleeved on the top frame. A push rod is slidably sleeved inside the cap-removing cylinder, and a sleeve plate extending into the sealed chassis is located at the bottom of the push rod. The device, through the construction of a sealed environment, the double-fixed opening and closing of the sealed cover, and the quantitative sealing design of the sampling cylinder, prevents waste liquid leakage, splashing, and radioactive gas diffusion during sampling. The system relies on multi-module collaboration to achieve multi-dimensional data acquisition. By quantifying corrosion, leakage, and sampling exposure risks, it intelligently generates risk warnings, and the data is traceable, significantly improving sampling safety, reliability, and the standardization of nuclear facility waste liquid management.

The present application relates to radioactive gas detection and sandstone type uranium exploration technical field, especially a soil radon emission rate measuring device and its sandstone type uranium ore prospecting method, including gas collecting mechanism, including PVC gas collecting cylinder, the top of PVC gas collecting cylinder is provided with sealing cover, the top of sealing cover is provided with atmospheric temperature and humidity pressure sensor and internet of things antenna respectively, the bottom of PVC gas collecting cylinder is installed with soil temperature and humidity sensor;Detection mechanism, it is cylindrical sealing mechanism, including chip storage module, photon counter.The present application realizes the underground in-situ stable measurement of soil radon emission rate by vertically burying PVC gas collecting cylinder in a certain depth under the ground, makes radon diffuse and accumulate naturally in the relatively closed and stable space from bottom to top, avoids the sealing problem and wind field interference under the open environment condition of the ground.In addition, cooperating with internet of things remote transmission technology, long-term continuous automatic observation and unattended can be realized, which significantly improves the field exploration efficiency.

The invention is applicable to the field of nuclear power detection, and discloses a detection method and a monitoring system for radioactive gas in a chimney of a nuclear facility, and the method comprises the following steps: S1, measuring a numerical value without aerosol particles by using a high-purity germanium detector to obtain a background counting rate nb, and S2, measuring an aerosol standard substance by using the high-purity germanium detector to obtain detection efficiency E; s3, transmitting the aerosol particles in the chimney of the nuclear facility to an ionization unit, and ionizing the aerosol particles by the ionization unit; s4, measuring the mass of the aerosol particles at the two ends of the sampling tube by the optical aerosol particle size spectrometer, and obtaining an aerosol penetration coefficient T through two times of mass measurement; and S5, starting a high-purity germanium detector to detect the ionized aerosol particles in the step S3, and calculating the activity concentration of the radioactive aerosol gamma nuclide according to the background counting rate nb in the step S1, the detection efficiency E in the step S2 and the aerosol penetration coefficient T in the step S4.

The utility model is applicable to the technical field of air purifiers, and discloses a circulating type toxic gas purifier which is applicable to purification of one or more gases such as radioactive gases, acid gases, alkaline gases, hydrogen sulfide, mercury vapor and the like. The modified activated carbon or the modified nano carbon fiber is used as an adsorption purification material of the purification module, so that the new purification module has higher adsorption capacity and adsorption selectivity, the purification efficiency of the purification machine can be improved, and the purification module can stably play a purification role when the purification machine is used for a long time in a high-humidity environment. The pulse discharge mechanism is arranged above the first air outlet of the air inlet fan, and the pulse discharge mechanism can be periodically started, so that air entering the machine shell can be ionized before entering the purification module, and when the ionized air enters the purification module, the air can be purified by the pulse discharge mechanism. The germs adsorbed on the modified activated carbon and the modified nano carbon fiber can be killed.

The invention relates to the technical field of radioactive gas sampling monitoring, and provides a wide-range airborne radioactive sampling monitoring system which comprises a sample introduction pipeline, a sample introduction pipeline, a first flushing pipeline, a first flushing bypass, a monitoring pipeline, a second flushing pipeline and a second flushing bypass, and the sample introduction pipeline is used for sample gas circulation. The flushing pipeline and the flushing bypass are arranged to respectively flush the sampling pipeline and the monitoring pipeline, so that a flushing object can be conveniently selected for flushing according to the actual flushing requirement, and the first flushing bypass and the sampling pipeline are mutually connected in parallel on the sampling pipeline; the second flushing pipeline is communicated between the sample inlet pipeline and the sample outlet pipeline, so that flushing gas cannot enter the sample outlet pipeline, and the flushing gas is prevented from interfering with conventional electrical control on the sample outlet pipeline due to the fact that the electrical regulation and control equipment is connected to the sample outlet pipeline during use and the flushing gas cannot enter the sample outlet pipeline. The use is convenient.

The application provides a method and system for real-time evaluation of adsorbent performance for radioactive gas treatment, and relates to the technical field of environmental monitoring. The method comprises the following steps: deploying a plurality of radioactivity sensors, temperature sensors and humidity sensors at different depths in the axial and radial directions of the adsorbent bed layer, collecting the radioactivity concentration, temperature and humidity at each position in real time through the sensors; and arranging ventilation impedance sensors and organic volatile sensors at the inlet and outlet of the adsorption unit and inside the bed layer, and synchronously collecting the ventilation impedance and the concentration of organic volatiles. The application realizes the global three-dimensional monitoring of the adsorption performance of the adsorbent, the accurate correction of multiple factors and the automatic discrimination of the safety threshold.

The invention relates to a radioactive gas extraction device with an external irradiation shielding function and a manufacturing and using method thereof. The device comprises a shell (1), a gas guide joint nut (2), a gas guide tube (3), a gas outlet joint (4), a gas outlet joint nut (5), a heating layer (6) and an external shielding layer (7), a radioactive gas to-be-extracted product is arranged in the shell (1), the gas guide connector nut (2) is communicated with the interior of the shell (1) through the gas guide pipe (3), the gas outlet connector nut (5) is communicated with the interior of the shell (1) through the gas outlet connector (4), and a heating layer (6) and an outer shielding layer (7) are sequentially arranged on the outer side of the shell (1). Compared with the prior art, the external radiation shielding function of the device is expected to achieve the effects of a traditional extraction hot chamber and an extraction furnace, and meanwhile, conditions can be created for continuous extraction of radioactive gas.

The utility model discloses a gas collection type toxic gas purifier which comprises a shell, a moving arm, a gas collection hood, a purification mechanism, a suction fan and a suction hood, wherein the purification mechanism, the suction fan and the suction hood are arranged in the shell; an exhaust outlet is formed in the side wall of the shell, and the suction fan is used for sucking outside air into the moving arm from the air collecting hood, then sucking the outside air into the shell, sucking the air purified by the purification mechanism into the air suction hood and then exhausting the air from the exhaust outlet; the moving arm comprises a plurality of sections of arm bodies, cylinders arranged at the end parts of the arm bodies, and rotating shafts for rotationally connecting the adjacent cylinders; and inner cavities of the arm body and the cylinder body are communicated with each other. By arranging the multiple sections of arm bodies capable of freely rotating and extending, the gas collecting hood can be close to places where gas pollutants are generated as much as possible to cover pollution sources at different positions, overflow of the gas pollutants is avoided to the maximum extent, and the air quality of a laboratory is ensured. The purifier is suitable for purifying radioactive gas, acid gas, alkaline gas, hydrogen sulfide, mercury steam and VOC organic gas.

The application discloses a surface pollution simulation detection method, device and system, and relates to the technical field of pollution simulation detection. The method comprises the following steps: constructing a fluid diffusion area three-dimensional space model according to space parameters of a to-be-detected area, and dividing the three-dimensional space model into a fluid domain space body grid and a ground surface boundary layer grid; adding radioactive gas particles, and setting the density and leakage rate of the radioactive gas particles; calculating the deposition velocity of the radioactive gas particles in the fluid domain space body grid and the particle concentration of the radioactive gas particles in the ground surface boundary layer grid according to a computational fluid dynamics method; further calculating the deposition flux and the deposition activity; assigning the deposition activity to NFC tags corresponding to the ground surface boundary layer grid, and detecting the NFC tags to complete surface pollution simulation detection. The embodiment of the application can more accurately predict the diffusion trend and deposition condition of radioactive pollutants, and improves the simulation accuracy.

The invention relates to the technical field of radioactive gas separation treatment, in particular to a method and system for recycling krypton and xenon in nuclear industry waste gas, and the system comprises a catalytic oxidation pond, a mixed combustion device, an alkali liquor washer, a drying bed, a krypton and xenon extraction device and a recycling tank, the catalytic oxidation pond is sequentially connected with the mixed combustion device, the alkali liquor washer, the drying bed, the krypton and xenon extraction device and the recovery tank through pipelines, the krypton and xenon extraction device adsorbs and analyzes krypton and xenon gas through an adsorbent, and the krypton and xenon gas is collected from waste gas. The method is simple in technological process, convenient to operate and high in separation efficiency, and krypton and xenon components in the nuclear industry waste gas can be efficiently separated and recycled through the multiple links of catalytic oxidation, gas combustion, alkali liquor washing, adsorption and desorption and the like.

The invention discloses a containment pressure reduction system, a reactor building and a containment pressure reduction method, which can realize pressure relief of a containment and simplify the structure of the containment pressure reduction system. The containment depressurization system comprises a heat exchange pool and a discharge depressurization loop. The discharge depressurization loop comprises a leading-out pipeline and a flow guide cover. The first end of the leading-out pipeline is communicated with the interior of the containment, and the second end of the leading-out pipeline extends into the heat exchange water tank, is positioned below the liquid level of cooling water in the heat exchange water tank and is used for leading the radioactive gas in the containment into the cooling water in the heat exchange water tank, so that radioactive substances in the radioactive gas are removed through the cooling water. The flow guide cover is arranged over the second end of the guiding-out pipeline in an inverted buckling mode, the top of the flow guide cover is located above the liquid level of cooling water in the heat exchange water pool, the bottom of the flow guide cover is submerged below the liquid level of the cooling water in the heat exchange water pool, and the flow guide cover is used for receiving the gas with the radioactive substances removed.