9 results about "Polonium" patented technology

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 invention discloses a polonium aerosol online monitoring system and method, and relates to the technical field of polonium monitoring. The system specifically comprises an aerosol sampling and enriching subsystem, an SERS detection subsystem and a data analysis and alarm subsystem, the aerosol sampling and enriching subsystem comprises an SERS substrate filter membrane, the SERS substrate filter membrane captures aerosol of gas to be detected, and a sample to be detected is formed on the SERS substrate filter membrane; the SERS detection subsystem irradiates a to-be-detected sample of the SERS substrate filter membrane and generates a Raman spectrum signal; and the data analysis and alarm subsystem receives the Raman spectrum signal from the SERS detection subsystem, and obtains the concentration of the polonium aerosol according to the polonium compound characteristic peak of the Raman spectrum signal and the correlation reference. The method is different from a traditional radioactivity detection method of polonium, complex sample pretreatment steps such as source preparation and extraction are not needed, and the time consumed by polonium aerosol in the measurement process is shortened.

The present invention relates to the technical field of radionuclide testing equipment, and specifically to a device and method for verifying a gas-solid reaction kinetic model of a polonium capture material. The verification device comprises: a gas supply assembly capable of outputting a set flow rate of test gas; a first temperature-controlled heating furnace, the inner cavity of which is connected to the output end of the gas supply assembly, the first temperature-controlled heating furnace being adapted to have a feeding mechanism and a first radiometer, the feeding mechanism being used to feed an evaporation crucible filled with polonium into the inner cavity of the first temperature-controlled heating furnace; and a second temperature-controlled heating furnace, the inner cavity of which is connected to the inner cavity of the first temperature-controlled heating furnace, the inner cavity of which is provided with a packed bed of capture material, and the gas outlet end of the second temperature-controlled heating furnace being adapted to have a second radiometer and a second pressure gauge, thereby meeting the requirements for studying the characteristics of Po-210 aerosol capture materials. The verification method is based on the aforementioned verification device.

The present application provides a radon gas detection method, apparatus, electronic device, and storage medium. The method includes: obtaining the number of first, second, and third particles generated by atomic decay of radon gas collected within a preset time period, where the first particle is emitted after the decay of radon-222, the second particle is emitted after the decay of polonium-218, and the third particle is emitted after the decay of polonium-214; determining a first humidity value based on a first ratio between the number of second or third particles and the number of first particles, where the smaller the first ratio, the greater the first humidity value; determining a first calibration coefficient based on the first humidity value, where the smaller the first humidity value, the smaller the first calibration coefficient; and determining a first radon gas concentration value based on the first calibration coefficient and the number of fifth particles, where the fifth particle is at least one of the second and third particles. This avoids the need for an additional humidity sensor and reduces product production costs.

This invention discloses a method for measuring the activity of radioactive polonium aerosol in a lead-bismuth reactor, belonging to the field of radioactive material measurement technology. 210 Po solution was used to prepare test samples with different activity ranges and different collection carriers, and the activity was measured using an energy dispersive spectrometer. A correlation between the measured activity and the theoretical activity was then established to calibrate the measured activity of actual samples. This invention employs the above-mentioned method for measuring the activity of radioactive polonium aerosol in a lead-bismuth reactor, by flexibly establishing a correlation between the measured activity and the theoretical activity within a certain activity range. 210 The linear correlation between the theoretical activity and the measured activity of the Po standard solution enables immediate measurement without disturbing the original sample, greatly ensuring the accuracy of the measurement. This is of great significance for timely and effective protection in lead-bismuth reactors. At the same time, this method can also be applied to other environments to quickly and accurately obtain the true activity of polonium-containing samples.

A diagnostic device and method detect target molecules in a liquid sample using radioisotopes that undergo alpha decay. The liquid sample is introduced onto a first portion of a permeable membrane, where its target molecules chemically bind to molecular tags. Each molecular tag includes both an alpha-emitter and a capture molecule designed to bind to the target molecule. The sample, including any bound target molecules, undergoes capillary flow to a second portion of the membrane, where an alpha-particle detector detects any bound alpha-emitters. The alpha-emitters may be radioactive nanoparticles (e.g. polonium-210) coated with an environmental protectant (e.g. gold). The detector may include CMOS diodes or a charge-coupled device. The device may include an indicator that signals when the detector detects alpha-particles above a given threshold in the second portion.

The invention discloses a fission reactor adopting a lithium lead alloy as a coolant, and belongs to the field of nuclear fission reactors. Aiming at the problems of high radiotoxicity of polonium-210 in the existing lead-bismuth cooled reactor and difficulty in engineering realization caused by overhigh melting point of a pure lead cooled reactor, the invention provides a fission reactor scheme taking a lithium-lead alloy as a coolant, and the fission reactor scheme has the following advantages: 1, the generation of polonium-210 is fundamentally eliminated, and the radioactivity safety performance is improved; 2, the melting point of the lithium-lead alloy is lower than that of pure lead, and engineering implementation is more feasible; the invention provides an innovative solution for solving the contradiction between the safety and the engineering feasibility of the current lead bismuth or pure lead cooling reactor, and has important engineering application value.

This invention relates to the field of radiation protection technology, specifically to a Po-210 protection device for high-concentration scenarios and its usage method. The protection device includes a protective hood with a viewing window on one side. A protective filter box is fitted to the side of the hood with the viewing window, and a blower is fitted to the air inlet of the filter box. The filter box includes a filter housing, the inner cavity of which is filled with impregnated carbon. The impregnated carbon is a material prepared by polonium-specific adsorption metal impregnation treatment. When the protective hood is worn over the operator's head, it can treat the gas inhaled by the operator through the filter box, effectively filtering Po-210 in the gas space and actively supplying air to the protection device. This effectively avoids increased ventilation resistance caused by the filter material inside the filter box, ensuring smooth breathing for the operator. It can be used for the safety protection of operators in scenarios where there is a high concentration of Po-210 in the gas space during a leak in a fourth-generation advanced fast reactor pipeline. The usage method is based on the aforementioned protection device.

The invention discloses a method for measuring activity of radioactive polonium aerosol in a lead-bismuth reactor, which belongs to the technical field of radioactive substance measurement, and comprises the following steps of: preparing samples to be measured with different activity ranges and different collection carriers by using a 210Po solution, and measuring the activity by using an energy disperse spectroscopy; according to the method for measuring the activity of the radioactive polonium aerosol in the lead-bismuth reactor, the activity of the radioactive polonium aerosol is measured, and then the correlation between the measured activity and the theoretical activity is established so as to be used for calibrating the measured activity of an actual sample. By flexibly establishing the correlation linear relation between the theoretical activity and the measurement activity of the 210Po standard solution within a certain activity range, immediate measurement can be realized under the condition of not disturbing an original sample, and the measurement accuracy is ensured to a great extent, which is of great significance to timely and effective protection implementation in a lead-bismuth reactor and has a wide application prospect. And meanwhile, the method can also be suitable for quickly and accurately acquiring the real activity of the polonium-containing sample in other environments.