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Device and method for testing gas-liquid interfacial corrosion of simulated nuclear waste liquid storage tank

A testing device and testing method technology, applied in measurement devices, weather resistance/light resistance/corrosion resistance, instruments, etc., can solve the problems of inability to simulate corrosion, inability to obtain direct evidence of corrosion mechanism, etc., achieve low cost, improve reliability, Control precise effects

Active Publication Date: 2019-02-22
INST OF OCEANOLOGY - CHINESE ACAD OF SCI +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0004] The invention proposes a test device and method for simulating the corrosion of the gas-liquid interface of a nuclear waste liquid storage tank, which simulates the corrosion situation of the inner wall of the nuclear waste liquid storage tank, and solves the problem that the electrochemical corrosion test method in the prior art cannot simulate nuclear waste liquid Corrosion of the inner wall of a storage tank without direct evidence of its corrosion mechanism

Method used

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  • Device and method for testing gas-liquid interfacial corrosion of simulated nuclear waste liquid storage tank
  • Device and method for testing gas-liquid interfacial corrosion of simulated nuclear waste liquid storage tank
  • Device and method for testing gas-liquid interfacial corrosion of simulated nuclear waste liquid storage tank

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Effect test

Embodiment 1

[0052] See attached figure 1 , a test device for simulating the corrosion of the gas-liquid interface of a nuclear waste liquid storage tank according to the present invention includes a sealing device 1, the sealing device 1 is a transparent glass container, the inside of the sealing device 1 has a cavity, and the top of the sealing device 1 is arranged There is a sealing cover 2 for sealing the cavity, and the sealing cover 2 is a rubber plug; a gas generator 3 is arranged in the cavity, and the gas generator 3 is an open glass container, and the gas generator 3 is filled with solid reactants. The sealing cover 2 is provided with an infusion tube 4 right above the gas generator 3, and the infusion tube 4 can deliver liquid reactants capable of chemically reacting with solid reactants to produce carbon dioxide / oxygen in the gas generator 3, and the infusion tube 4 is connected to the gas generator 3. The outside air is not connected, and the infusion tube 4 is a syringe; one ...

Embodiment 2

[0062] On the basis of Example 1, the temperature of the water bath was adjusted to 34°C, and other parameters remained unchanged, and the corrosion test experiment of the working electrode 7 was carried out again. The experimental results are as attached Figure 4 And attached Figure 5 shown.

[0063] attached by Figure 4 It can be seen that after the ambient temperature rises, the working electrode 7, that is, the metal sample is corroded by the nuclear waste liquid simulation solution, resulting in shorter pitting initiation time; Figure 5 It can be seen that after the ambient temperature rises, the change rate of the pH value at the nuclear waste liquid interface also accelerates; Figure 4 Under the obtained pitting initiation time, all the different concentrations of carbon dioxide correspond to the same pH value of 12.38, which is the pH critical point at which the working electrode 7 corrodes (ie, pitting corrosion) at a temperature of 34°C ; Due to the increase ...

Embodiment 3

[0065] On the basis of Embodiment 1, the measurement probe 9, that is, the plane pH electrode, is inserted into the nuclear waste liquid simulation liquid at 1 cm below the liquid level for monitoring, and other parameters remain unchanged, and the corrosion test experiment of the working electrode 7 is carried out again. The experimental results are as follows attached Image 6 - attached Figure 9 shown.

[0066] attached by Image 6 - attached Figure 9 It can be seen that in this embodiment, the pH values ​​at 1 cm below the gas-liquid interface of all nuclear waste liquid simulation liquids are greater than 12.6, that is, greater than the critical pH value of 12.46 for pitting corrosion of the working electrode 7. Therefore, in this embodiment The middle working electrode 7 does not corrode 1 cm below the gas-liquid interface of the nuclear waste liquid simulation liquid. This further proves that the corrosion of nuclear waste liquid only occurs at the gas-liquid inte...

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Abstract

The invention provides a device and a method for testing the gas-liquid interfacial corrosion of a simulated nuclear waste liquid storage tank. The device comprises a seal device, wherein a cavity isformed inside the seal device, and a seal cap is arranged at the top of the seal device; a gas generator is arranged in the cavity, and a liquid delivery pipe is arranged on the seal cap and right above the gas generator; and an electrolytic tank is arranged on one side of the gas generator, and a nuclear waste liquid stimulated liquid is arranged in the electrolytic tank, and a reference electrode, a work electrode, a counter electrode and a measuring probe are arranged on the seal cap and above the electrolytic tank. The invention further provides a method for testing the gas-liquid interfacial corrosion of a simulated nuclear waste liquid storage tank. The corrosive characteristic of nuclear waste liquid at the gas-liquid junction on the inner wall of the storage tank can be truly stimulated, and the corrosion rule and corrosion mechanism of the area are explored by changing the gaseous component concentration in the atmosphere inside the seal device, and the gaseous component concentration can be accurately controlled. The testing device is simple, is low in cost, simple in operation and high in experimental efficiency, and has an important guiding significance.

Description

technical field [0001] The invention relates to the technical field of electrochemical corrosion, in particular to a test device and method for simulating the gas-liquid interface corrosion of a nuclear waste liquid storage tank. Background technique [0002] The operation, maintenance and decommissioning of nuclear power plants will produce a large amount of radioactive waste water, that is, nuclear waste liquid, plus the nuclear waste liquid brought by nuclear weapons in history. These nuclear waste liquids are radioactive and very harmful, so they cannot be discharged directly. Currently Temporary storage in storage tanks is required. Nuclear waste liquid is divided into medium and low radioactive nuclear waste liquid and high radioactive nuclear waste liquid. High radioactive nuclear waste liquid means that the radiation concentration is greater than 3.7×10 10 Bq / L waste liquid, this kind of radioactive nuclear waste liquid cannot be safely released into the environment...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01N17/02G01N17/04
CPCG01N17/006G01N17/02G01N17/043
Inventor 徐玮辰杨黎晖张斌斌李田田李言涛侯保荣段继周
Owner INST OF OCEANOLOGY - CHINESE ACAD OF SCI