Nuclear power plant radioactive fluid waste online sampling device and method

A sampling device and radioactive technology, applied in the field of nuclear power, can solve the problems of safety, economy, restriction of nuclear power plant operation and management level, large measurement error of gamma spectrometer measuring device, etc., and achieve The effect of low procurement and operation and maintenance costs, improved safety and economy, and improved operation and management levels

Inactive Publication Date: 2016-05-04
中广核工程有限公司 +1
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0005] 1) The gamma spectrometer measurement device has large measurement errors and low accuracy, which restricts the improvement of the operation and management level of nuclear power plants, and often results in high costs for waste package transportation and disposal outside the plant, which is not conducive to the imp

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  • Nuclear power plant radioactive fluid waste online sampling device and method
  • Nuclear power plant radioactive fluid waste online sampling device and method

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Embodiment Construction

[0036] In order to make the purpose, technical solution and technical effect of the present invention clearer, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific implementation methods. It should be understood that the specific implementations described in this specification are only for explaining the present invention, not for limiting the present invention.

[0037] see figure 1 and figure 2 As shown, the nuclear power plant radioactive fluid waste online sampling device of the present invention includes: a sampling part 10 sealedly connected with the fluid pipeline 60 and provided with a storage space 104; a movable rod 20 sealed and housed in the storage space 104 and provided with an annular sampling space 202; A driving device 30 for driving the movable rod 20 to reciprocate in the receiving space 104 , and a discharge port 106 communicating with the receiving space 104 and capable of discharging ...

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Abstract

The invention discloses a nuclear power plant radioactive fluid waste online sampling device which comprises a sampling part sealedly connected to a fluid pipeline, a movable rod sealedly accommodated in an accommodating space, and a driving device sealedly mounted on the sampling part; the sampling part is provided with the accommodating space and a sample discharge port communicating with the accommodating space; the movable rod is provided with a concave sampling space and can perform reciprocating motion between a sample discharge position and a sampling position; the driving device drives the movable rod to perform reciprocating motion between the sample discharge position and the sampling position in the accommodating space; when the movable rod is located at the sampling position, the movable rod enters the fluid pipeline, and a fluid sample enters the concave sampling space; when the movable rod is located at the sample discharge position, the concave sampling space corresponds to the sample discharge port, and the fluid sample carried in the concave sampling space flows into a shield sampling bottle sealed connected on the sample discharge port from the sample discharge port. In addition, the invention also discloses a nuclear power plant radioactive fluid waste online sampling method.

Description

technical field [0001] The invention belongs to the technical field of nuclear power, and more specifically relates to an on-line sampling device and method for radioactive fluid waste in a nuclear power plant. Background technique [0002] At present, in some nuclear power plants, the radioactive solid waste treatment system adopts a mature cement solidification process to process radioactive fluid waste (such as waste resin, etc.), and the radioactive fluid waste is solidified by cement to form the final waste package. [0003] Nuclear power plants usually use γ-spectrometer measuring devices to analyze cement-solidified waste packages to obtain the activity of radioactive fluid waste in the waste packages and the surface dose rate data of the waste packages, which provide sources for the formulation of safe off-site transportation and disposal plans for waste packages. Item basis. [0004] However, the existing gamma spectrometer measuring device has the following defect...

Claims

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Application Information

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IPC IPC(8): G01N1/10
CPCG01N1/10G01N2001/1031
Inventor 严勇温宁华潘跃龙邓先宽
Owner 中广核工程有限公司
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