125 results about "Radioactive gas" patented technology

The invention discloses a radioactive gas detection device and a detection method.The radioactive gas detection device is applied to detection of radioactive gas containing target nuclides and comprises an adsorption assembly, a sampling assembly, a monitoring assembly, a desorption assembly, a detection assembly, a first control valve set and a controller, the sampling assembly, the adsorption assembly and the monitoring assembly are sequentially communicated; the adsorption assembly is further communicated with the detection assembly, and the controller is configured to control the first control valve group to enable the adsorption assembly and the sampling assembly as well as the adsorption assembly and the monitoring assembly to be in a disconnected state when the monitoring assembly monitors that the radioactive gas passing through the adsorption assembly contains target nuclide; the adsorption assembly and the detection assembly are in a communication state, and the detection assembly is controlled to execute detection operation on the target nuclide released from the adsorption assembly so as to obtain the content of the target nuclide. The radioactive gas detection device can improve the detection precision of the target nuclide in the radioactive gas.

The invention relates to the technical field of nuclear radiation detection management, and discloses a nuclear radiation detection management system based on artificial intelligence, comprising: a dynamic sensing module which detects nuclear radiation through quantum sensing to obtain radiation data, captures NV color center fluorescence intensity, analyzes to obtain gamma ray dose rate, constructs a nanoscale olfactory receptor simulation structure, and sends the radiation data to a control module; radioactive gas is detected and cooperatively monitored; the reasoning calculation module is used for analyzing space-time correlation based on radiation data, optimizing algorithm to accelerate result output, adjusting calculation complexity by calculating dynamic weight distillation, and correcting data transmission in real time; the decision management module is used for constructing a four-dimensional causal graph based on the radiation data, performing intervention simulation, evaluating a decision long-term effect, screening an optimal decision, and performing adversarial training based on historical repair case data; and the fusion cooperation module is used for establishing a cross-mechanism federated learning framework, carrying out hash operation on the radiation data, and establishing an NFT (Network Fourier Transform) on a block chain through an intelligent contract for query, verification and transaction.

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 present invention relates to the technical field of radioactive gas adsorbents, and in particular to a modification method for increasing the adsorption capacity of activated carbon for radon gas. The present invention performs fluorination modification on the activated carbon by pre-reacting the activated carbon in an F2 / N2 mixed gas atmosphere with an F2 volume concentration of 5%, and then reacting in an F2 / N2 mixed gas atmosphere with an F2 volume concentration of 8-15%, so as to increase the adsorption capacity of the activated carbon for radon gas. The present invention provides a modification method for increasing the adsorption capacity of activated carbon for radon gas, and increases the adsorption capacity of activated carbon for radon gas by fluorination modification of the activated carbon. The method of the present invention overcomes the problems in the prior art that the micropore adjustment technology is not highly controllable, the preparation method is complicated, and the selective adsorption capacity of radon gas is limited.

The invention discloses a device and a method for treating and recycling radioactive CO2 gas in nuclear-grade waste combustion products. The device comprises a combustion unit, a combustion unit and a recycling unit, the filtering unit is connected with the combustion unit and used for filtering mixed gas containing radioactive CO2 generated in the nuclear-grade waste combustion process; the cooling unit is connected with the filtering unit; the purification unit is connected with the cooling unit; the trapping and regenerating unit is connected with the purifying unit; and the circulating unit is connected with the combustion unit and the trapping and regenerating unit. The device is simple in structure, the adsorption material is convenient to regenerate and replace, the device can be repeatedly used for a long time, CO2 can be selectively adsorbed from nuclear power plant mixed waste gas or other mixed gas, the development requirements of carbon emission control and carbon neutralization are met, environmental radiation pollution caused by nuclear power plant waste gas or other waste gas in the nature can be relieved, and the environmental pollution is reduced. Meanwhile, carbon isotope resources can be effectively recycled, the process is safe and controllable, and the risk of radioactive substance leakage is avoided.

The invention discloses a gas detection system, the gas detection system is used for detecting target elements in gas to be detected, and the gas detection system comprises a gas inlet unit, an impurity removal unit, a sampling unit and a detection unit; the gas outlet end of the gas inlet unit is connected with the gas inlet end of the impurity removal unit, the gas outlet end of the impurity removal unit is connected with the gas inlet end of the sampling unit, the gas outlet end of the sampling unit is connected with the gas inlet end of the detection unit, the impurity removal unit is used for filtering impurities in gas to be detected, and the sampling unit is used for adsorbing target elements from the gas to be detected and desorbing the target elements. And the detection unit is used for detecting the target element desorbed from the sampling unit. The gas detection system provided by the invention can improve the detection precision of low-concentration radioactive gas.

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 provides a radioactive waste gas treatment system and method suitable for a miniature reactor, the waste gas treatment system comprises a gas exhaust pipeline, a retention bed, a gas cavity, a vacuum source and a high efficiency filter, the retention bed is communicated with the gas exhaust system through the gas exhaust pipeline, and the gas cavity is communicated with the retention bed through the gas exhaust pipeline; the vacuum source is communicated with the air cavity through an exhaust pipeline; the high-efficiency filter is arranged between the air cavity and the vacuum source; the waste gas treatment system is in a negative pressure state through vacuumizing of the vacuum source, radioactive waste gas generated by the exhaust system enters the retention bed and the high-efficiency filter through the exhaust pipeline under the action of negative pressure and then gradually decays after being intercepted, and the decayed radioactive gas enters the downstream exhaust system through the exhaust valve. According to the radioactive waste gas treatment system, passive purification and safe emission of reactor radioactive waste gas can be achieved, and the treatment capacity and safety of the system are improved.

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.

The invention relates to the technical field of detection equipment in the aspects of radiation protection and environmental protection, and provides a portable radioactive gas sampling device which comprises a movable case, a partition plate and a sampling mechanism, the sampling mechanism comprises a gas inlet connector, a vacuum pump, a gas cylinder, a gas outlet connector and a communicating pipeline, the gas inlet connector, the vacuum pump, the gas cylinder and the gas outlet connector are fixedly arranged on the partition plate, and the gas inlet connector, the vacuum pump, the gas cylinder and the gas outlet connector are located on the same side of the partition plate; the communicating pipeline is located on the other side of the partition plate. The gas inlet connector, the vacuum pump, the gas cylinder, the gas outlet connector and the communicating pipeline are arranged in the movable case, rapid sampling of gas can be achieved by means of the series connection relation of the gas inlet connector, the vacuum pump, the gas cylinder, the gas outlet connector and the communicating pipeline, all the components are reasonably arranged by arranging the partition plate and separating the communicating pipeline from other components through the partition plate, and the sampling efficiency is improved. Therefore, the operation efficiency of the sampling device is improved.

The invention belongs to the technical field of gas oxyhydrogen concentration detection in nuclear power plant primary loop related containers, and particularly relates to a sampling detection method for gas oxyhydrogen concentration in nuclear power plant primary loop related containers. The in-container gas component confirmation module is used for confirming the current working state of a container which is about to be subjected to gas sampling to detect the hydrogen and oxygen concentration, so as to confirm the main components of gas in the container; the in-container gas sampling module adopts different sampling exhaust paths according to different components of the gas in the container after confirming the main components of the gas in the container; and the in-container gas detection module is used for detecting hydrogen and oxygen concentrations of gas in the container by using an instrument. Risks of internal irradiation, large deviation of measurement results, hydrogen-oxygen mixed explosion, violation of laws and regulations caused by radioactive gas pollution diffusion and the like due to the fact that personnel inhale radioactive waste gas by mistake in a gas sampling and monitoring process in a container are avoided.

The invention particularly relates to a vacuum off-line sipping simulation device for a fuel assembly. The vacuum off-line sipping simulation device comprises a sipping tube consisting of an outer tube and an inner tube, a radioactive gas detection device, a vacuum device, a heating rod and a crevasse opening and closing device, the top of the outer cylinder is provided with a gas path interface, the top of the inner cylinder is provided with a vacuum interface, the outer cylinder is connected with a radioactive gas detection device through the gas path interface, and the inner cylinder is connected with a vacuum device through the vacuum interface; the heating rod is placed in the inner cylinder; the crevasse opening and closing device is connected to the outer cylinder in an up-down rotating mode, and opening or closing of the crevasse of the inner cylinder is achieved. According to the fuel assembly vacuum off-line sipping simulation device, simulation of crevasse sizes and crevasse positions of different sizes of the fuel assembly is achieved.

The invention discloses a method for measuring a body source dose rate under strong line source interference. The method comprises the following steps: step 1, measuring a gamma dose rate Dair at the same height in a nearby non-pipeline interference area through a gamma dose rate monitor; 2, calculating to obtain a gamma dose rate contribution ratio as a constant k; 3, measuring gamma dose rate measured values M1 and M2 at h1 and h2 positions on the central axis of the pipeline through a gamma dose rate monitor; 4, the gamma dosage rate caused by the air in the monitoring area is evaluated according to the value k, the M1 and the M2, and rapid early warning is carried out. The gamma dosage rate caused by the ambient air can be obtained by changing the position of one gamma dosage rate monitor; according to the method, the problem that ambient air radioactivity early warning cannot be realized through a gamma dose rate instrument in a part of strong radioactive pipeline passing areas in a plant is solved, the monitoring cost of radioactive gas leakage in the plant can be expected to be reduced, and the monitoring timeliness is improved.

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 invention relates to the technical field of nuclear facility safety, and discloses a radioactive gas treatment device, a nuclear facility ventilation system and a nuclear facility pressure relief method.The radioactive gas treatment device comprises a box body and a partition plate, an absorption medium is arranged in the box body, an air inlet and an air outlet are formed in the box body, the partition plate is arranged in the box body, and one end of the partition plate is connected with the inner top wall of the box body; one end of the box body is provided with an air inlet, the other end of the box body is located in the absorption medium, and a gap is reserved between the other end of the box body and the inner bottom wall of the box body. When overpressure exists in a high-radioactivity area, high-temperature smoke containing dust particles such as radioactive aerosol enters the absorption medium through the air inlet, and the dust particles such as the aerosol in the smoke collide with liquid drops in the absorption medium in an inertial mode and are intercepted; the high-temperature flue gas is introduced into the absorption medium, so that the high-temperature flue gas is intercepted in the absorption medium, dust particles such as aerosol in the pressure relief gas can be effectively removed, the purposes of purification and dust removal are achieved, meanwhile, the temperature of the high-temperature flue gas is reduced when the high-temperature flue gas passes through the absorption medium, and diffusion of a large number of high-radioactive substances to a low-pollution area is effectively avoided.

The invention belongs to the field of water chemical analysis, and particularly relates to a method for measuring potassium ions in boron-containing water of a nuclear power plant, which comprises the following steps: step 1, calibrating a potassium ion selective electrode by using a potassium ion standard solution to obtain a potassium ion concentration-electromotive force signal standard curve; step 2, using hydrogen peroxide to adjust the boron-containing water sample to be detected to be neutral through oxidation reduction; step 3, adjusting the boron-containing water sample of the to-be-detected sample to be neutral by using hydrochloric acid to obtain a treated boron-containing water sample of the to-be-detected sample; and step 4, inserting the calibrated potassium ion selective electrode into the treated boron-containing water sample of the sample to be detected, and calculating the potassium ion concentration of the sample to be detected through the electromotive force signal according to the standard curve. According to the method, human intervention and medicament use are effectively reduced, radioactive gas release is reduced, and the potassium ion concentration in the dosing system can be rapidly and accurately analyzed.

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 embodiment of the invention discloses a ventilation filtering device, a filtering device performance detection method and a control device thereof. The ventilation filtering device comprises a filtering assembly, an inlet pipeline, an outlet pipeline, an inlet monitoring module and an outlet monitoring module, the filtering assembly is used for filtering radioactive gas, the inlet pipeline and the outlet pipeline are communicated with an inlet and an outlet of the filtering assembly respectively, and the inlet monitoring module is arranged on the inlet pipeline; the monitoring module is arranged on the inlet pipeline and used for monitoring the particulate matter concentration of multiple particle size intervals in the radioactive gas in the inlet pipeline, and the outlet monitoring module is arranged on the outlet pipeline and used for monitoring the particulate matter concentration of multiple particle size intervals in the radioactive gas in the outlet pipeline. Through the inlet monitoring module and the outlet monitoring module, the inlet concentration and the outlet concentration of particulate matters passing through the filter assembly are monitored in real time, the running state of the filter assembly is judged, and tedious detection operation and pollution to the filter assembly are avoided. The filtering assembly is monitored in real time, and the detection result is timely and accurate.

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 present invention discloses a cathode discharge tube, belonging to the field of optical and ionization devices. It includes a body part, a cathode discharge part and a connection part. Among them, the body part forms a closed hollow accommodation space, and a radioactive gas and / or a protective gas is filled in the accommodation space; the cathode discharge part is arranged in the accommodation space, one end of the connection part is exposed outside the body part and is suitable for being connected to the negative pole of a power supply; the other end is hermetically passed through the body part and is connected to the cathode discharge part. In the present invention, the cathode discharge part is always located under a protective atmosphere composed of a radioactive gas and / or a protective gas, without contacting with air or oxygen, ensuring that the cathode is not oxidized, prolonging the service life of the emission cathode product, and reducing the use cost of the product.