Radioactive waste gas treatment method and system for isotope production line

Abstract

The embodiment of the invention provides a radioactive waste gas treatment method and system for an isotope production line, and the method comprises the steps: S1, treating radioactive waste gas through a first drying device, and monitoring the first humidity of the waste gas leaving the first drying device; s2,comparing the first humidity of the waste gas with a preset humidity value, if the first humidity of the waste gas is larger than or equal to the preset humidity value, switching the first drying device into a second drying device to achieve continuous treatment of the radioactive waste gas, andexecuting S3; s3, feeding hot air into the first drying device, and monitoring the first humidity of the hot air leaving the first drying device; and s4, judging whether the first humidity of the hot air is smaller than the preset humidity value or not, and if so, completing regeneration; and if not, continuing to execute S3. According to the embodiment of the invention, the first drying device and the second drying device are switched through the switching device, and the switched drying device is subjected to regeneration treatment, so that the replacement of silica gel in the drying device is reduced while the radioactive waste gas treatment is not influenced.

Description

technical field [0001] The invention relates to a method and system for treating radioactive waste gas of an isotope production line. Background technique [0002] During the production process of isotope irradiation, a small amount of hydrogen-containing waste gas entrained with radionuclides will be produced. The radionuclides entrained in the waste gas are mainly krypton, xenon and a certain amount of iodine. For hydrogen-containing waste gas, there are currently two treatment processes: pressurized storage decay and activated carbon retention adsorption decay. [0003] The principle of pressurized storage and decay is as follows: radioactive waste gas containing fission nuclides such as Xe\Kr enters a buffer tank first, then is compressed to 0.6-0.7Mpa by a compressor, and sent to a gas decay tank for centralized storage. After natural decay, after the activity of the nuclide with a short half-life is greatly reduced, the sample is analyzed. If the result meets the disc...

AI Technical Summary

Problems solved by technology

After the conventional activated carbon retention and decay process has been in operation for a period of time, the drying capacity and adsorption capacity of the silica gel on the drying bed and the activated carbon on the retention bed will be reduced due to environmental factors and operating conditions, which will affect the effect of the process on treating radioactive waste gas. Regular replacement of silica gel on the drying bed and activated carbon on the stagnant bed will affect the operation of exhaust gas treatment and increase the harm of radiation to personnel

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