Nuclear power plant radioactive fluid waste online sampling device and method

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...

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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 implementation plan of waste package transportation and disposal safety, economy

[0006] 2) The gamma spectrometer measurement device has a complex structure, expensive procurement costs, long installation and commissioning cycles, regular calibration of the measurement device, and relatively difficult operation and maintenance

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