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System and method for in-situ spectral measurement of corrosion behavior of reactor cladding material

A cladding material, in-situ spectroscopy technology, applied in the field of chemical analysis equipment, can solve problems such as unattainable, unrealistic conditions, and low efficiency

Pending Publication Date: 2020-12-25
NANJING UNIV OF AERONAUTICS & ASTRONAUTICS
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

This kind of pressurization method has low efficiency under the experimental conditions, does not meet the actual conditions of the experiment, and cannot reach a higher test pressure
More importantly, due to the inherent characteristics of the reaction vessel, the simulation system proposed by this design cannot allow the detection light to enter the reaction window, so it is impossible to perform online real-time spectral measurement to measure related experimental data

Method used

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  • System and method for in-situ spectral measurement of corrosion behavior of reactor cladding material
  • System and method for in-situ spectral measurement of corrosion behavior of reactor cladding material
  • System and method for in-situ spectral measurement of corrosion behavior of reactor cladding material

Examples

Experimental program
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Effect test

Embodiment 1

[0065] Measure the infrared spectrum changes of SiC under high temperature radiation conditions;

[0066] 0.6767 g of SiC powders with different particle sizes and 35 ml of deionized water were prepared into a suspension and put into the reaction kettle. After putting stainless steel magnets in the reaction kettle, the sealing cover was sealed and fastened with a wrench. Close the sampling valve, connect the carbon dioxide cylinder tube to the reactor sampling line, so that the pressure in the reactor reaches 1 Mpa, close the sampling valve, place the reactor on the lifting platform, and the irradiation window is perpendicular to the direction of the radioactive source. The irradiated aperture is the smallest, the source of the radioactive source is raised, and the heating is started after the height of the radioactive source is stable; the target temperature is 573.15K, after heating up and stirring for 1 hour, turn off the heating power supply, the pressure reaches 25Mpa, and...

Embodiment 2

[0069] The ultraviolet spectrum of the reactor's charge transfer at the interface;

[0070] Prepare a suspension of 0.06g FeCrAl alloy powder with a particle size of 50 nm and 35 mL of deionized water into the reactor, put a stainless steel magnet in the reactor, and use a wrench to seal and fasten the sealing cover . Close the sampling valve, connect the carbon dioxide cylinder tube to the reactor sampling line, so that the pressure in the reactor reaches 2 Mpa, close the sampling valve, connect the gas chromatograph to the reactor sampling line, and then place the reactor on the lifting platform Above, the irradiation window is perpendicular to the direction of the radioactive source, the irradiation aperture is the smallest, the radioactive source is raised and stirred for 1 hour at the same time, and the irradiation dose is 480 Gy / h. During the irradiation process, the deuterium lamp was used as the light source to inject from the irradiation window, and the reactant was ...

Embodiment 3

[0073] Measuring H of Zr-4 Alloy under High Temperature Radiation Condition 2 Because the reaction of zirconium water will produce hydrogen, it is indirectly proved that the reactor cladding material is corroded by measuring the hydrogen production by gas chromatograph;

[0074] 0.06g of Zr-4 alloy powder with a particle size of 50 nm and 35 mL of deionized water were prepared into a suspension and put into the reaction kettle, and a stainless steel magnet was placed in the reaction kettle, and the sealing cover was sealed with a wrench fasten. Close the sampling valve, connect the carbon dioxide cylinder tube to the reactor sampling line, so that the pressure in the reactor reaches 2 Mpa, close the sampling valve, connect the gas chromatograph to the reactor sampling line, and then place the reactor on the lifting platform above, the irradiation window is perpendicular to the direction of the radioactive source, the irradiation aperture is the smallest, the radioactive sourc...

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Abstract

The invention discloses a system and a method for in-situ spectral measurement of a corrosion behavior of a reactor cladding material. The method comprises the following steps of: firstly, putting thecladding material into a reaction kettle; creating a high-temperature and high-pressure environment in the reaction kettle; safely putting the reaction kettle into an irradiation field created by a radioactive source, wherein in an irradiation process, detection light can penetrate through an irradiation window in a heating mechanism and enters the reaction kettle; after the detection light is emitted, analyzing the change of the material in the reaction kettle on line by detection means such as a gas chromatographic analyzer, a liquid chromatographic analyzer and an infrared spectrometer; and analyzing a gas product extracted by a gas sampling pipeline of the reaction kettle through an on-line analysis system, so that the corrosion behavior of the cladding material under a high-temperature and high-pressure irradiation condition is known. Moreover, the stability of a simulation system is guaranteed through a pressure measuring pipeline, a pressure relief pipeline and a temperature sensor, and various dangers are avoided.

Description

technical field [0001] The invention relates to the technical field of chemical analysis equipment, in particular to a system capable of in-situ spectral measurement and a method thereof. Background technique [0002] The Fukushima incident once again sounded the alarm for human nuclear safety. As the future pillar energy of mankind, nuclear energy is developing rapidly. Nuclear energy safety, especially nuclear power safety, has become one of the core areas of national security in China and the world. Traditional nuclear fuel cladding materials due to hydrothermal reactions make the reactor lose off-site power supply. Under the circumstances, the heat removal system cannot work normally, which leads to a hydrogen explosion. Due to the urgent need to study new cladding materials and the high cost of in-reactor irradiation research, it is generally required to evaluate the materials in a complex coupling environment such as temperature, pressure, water environment and radiat...

Claims

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Application Information

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IPC IPC(8): G01N17/00G01N21/3577G01N21/33G01N30/02
CPCG01N17/00G01N21/33G01N21/3577G01N30/02
Inventor 马骏师鹏飞王运龙甘平平
Owner NANJING UNIV OF AERONAUTICS & ASTRONAUTICS
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