A kind of i-129 sampling device and sampling method

A sampling device and sampler technology, which is applied in the field of nuclear radiation monitoring to achieve the effects of reasonable design, efficient sampling, and easy popularization and use.

Active Publication Date: 2021-12-24
SHAANXI WEIFENG NUCLEAR ELECTRONICS +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

In the prior art, there is still a lack of I-129 continuous sampling device with simple structure and remarkable effect to remove the influence of Kr-85 applied in the reprocessing field of nuclear components

Method used

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  • A kind of i-129 sampling device and sampling method
  • A kind of i-129 sampling device and sampling method
  • A kind of i-129 sampling device and sampling method

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Embodiment Construction

[0055] Such as figure 1 As shown, the I-129 sampling device of the present invention includes a sampling line unit and a sampling detection unit; the sampling line unit includes a sampling gas inlet joint 1, a purge gas inlet joint 2 and a sampling gas outlet joint 3, and a sampling line unit Gas inlet pipe 4, purge gas inlet pipe 5 and sampling gas outlet main pipe 6; one end of the sampling gas inlet pipe 4 is connected to the sampling gas inlet joint 1, and the other end of the sampling gas inlet pipe 4 is connected to the sampling detection unit , the sampling gas inlet pipe 4 is sequentially provided with a first filter 7, a first stop valve 8, a first flow meter 9, a first electromagnetic reversing valve 10 and a direction from the sampling gas inlet joint 1 to the sampling detection unit The first regulating valve 11, a section of the sampling gas inlet pipe 4 between the first electromagnetic reversing valve 10 and the first regulating valve 11 is connected with a firs...

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Abstract

The invention discloses an I-129 sampling device and a sampling method. The device includes a sampling pipeline unit and a sampling detection unit; the sampling pipeline unit includes a sampling gas inlet joint, a purge gas inlet joint, a sampling gas outlet joint, and a sampling gas Intake pipe, purge gas inlet pipe and sampling gas outlet main pipe; the sampling gas inlet pipe is provided with a first filter, a first stop valve, a first flow meter, a first electromagnetic reversing valve and a first regulating valve, and the purge The gas inlet pipe is provided with a second filter, a second stop valve, a one-way valve, a second flow meter, a second electromagnetic reversing valve and a second regulating valve. The sampling detection unit includes a first iodine sampler, a second iodine sampler and an iodine detector. The device of the invention has a simple structure, can effectively remove the influence of Kr-85 on I-129, and at the same time realize high-efficiency sampling of I-129, has good application effect and is easy to popularize.

Description

technical field [0001] The invention belongs to the technical field of nuclear radiation monitoring, and in particular relates to an I-129 sampling device and a sampling method. Background technique [0002] In the reprocessing site of nuclear fuel elements, after long-term cooling, the radioactive gases in the fission products are mainly Kr-85 and I-129, and the half-life of I-129 is as long as 1.57×10 7 Years, long-term hazards to human body and environment. Therefore, in order to ensure the safety of the environment and operators, it is necessary to monitor the radioactivity of I-129 in the airborne effluent in the process pipeline of the nuclear fuel element reprocessing site. [0003] However, due to the low content of I-129 in the fission gas, and its activity differs from that of Kr-85 by at least 10 6 order of magnitude, for example, after five years of cooling a fuel rod with a burnup consumption of 62GW, the activity of Kr-85 is 7.06×10 12 The activity of Bq, I-...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G01T1/167G01T1/202G01T1/208G01T7/02
CPCG01T1/167G01T1/202G01T1/208G01T7/02
Inventor 常贤龙王欣张祥林杨康曲广卫郑皓贾红宝肖鹏飞赵江斌张伟
Owner SHAANXI WEIFENG NUCLEAR ELECTRONICS
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