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Device for online vacuum drying and regeneration of activated carbon of retention bed of nuclear power unit

A technology for vacuum drying and nuclear power units, which is applied in filter regeneration, nuclear engineering, radioactive purification, etc. It can solve the problems of unable to fundamentally remove the humidity of activated carbon, decrease the ability to absorb inert gas, and decrease the adsorption performance of activated carbon, so as to avoid radioactive solid waste The effect of increasing and reducing the difficulty of equipment manufacturing and shortening the regeneration time

Pending Publication Date: 2021-05-07
JIANGSU NUCLEAR POWER CORP +1
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AI Technical Summary

Problems solved by technology

[0003] The humidity of the activated carbon in the detaining bed after long-term operation gradually increases, and the ability to absorb inert gas decreases. During operation, the regeneration frequency of the main and auxiliary series of zeolite filters can only be increased to reduce the humidity of the gas entering the detaining bed, but the humidity in the activated carbon cannot be completely removed.
As the running time increases, the adsorption of activated carbon will tend to be saturated, and the adsorption performance of activated carbon for inert gases will continue to decline. By replacing the activated carbon method, the ability to adsorb inert gases by activated carbon in the stagnant bed can only be temporarily improved. There is a risk of common cause failure of activated carbon in the stagnant bed. Moreover, it is necessary to deal with a large amount of radioactive solid waste after replacement, increasing the reserve pressure of the power station

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  • Device for online vacuum drying and regeneration of activated carbon of retention bed of nuclear power unit

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Embodiment Construction

[0033] The present invention will be further described below by means of the accompanying drawings and specific embodiments.

[0034] Such as figure 1 As shown, the regeneration device includes a compressed air source 34 that introduces compressed air, an electric heater 4 that heats the output pipeline of the compressed air source 34, a test retention bed 27 that is connected to the heated output pipeline through a valve, and a refrigerated air dryer 22. , vacuum pump 23 and evacuation of the stagnant bed 32.

[0035] A compressed air supply switch 1, a flow meter 2 and an intake pressure gauge 3 are sequentially installed on the pipeline between the compressed air source 34 and the electric heater 4;

[0036] Install the following valves and instruments in sequence on the heated output pipeline.

[0037] Including heating flow regulating valve 5, heating circuit pressure gauge 6, thermometer I7, hygrometer I8, heating circuit bypass valve 9, radiation monitor 10, thermomet...

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Abstract

The invention belongs to a nuclear power station waste gas treatment technology, and particularly relates to a device for online vacuum drying and regeneration of activated carbon of a retention bed of a nuclear power unit. The device comprises a compressed air source for introducing compressed air, an electric heater for heating an output pipeline of the compressed air source, and a test retention bed, a refrigerated air dryer, a vacuum pump and an emptying retention bed which are sequentially connected with the heated output pipeline through valves. Under the condition that the retention bed activated carbon is not discharged, the adsorption performance of the activated carbon can be improved through an online vacuum drying regeneration technology and a zero emission mode, a new mode can be provided for retention bed activated carbon treatment, and an optimization reference is provided for subsequent design and operation of a nuclear power unit inert gas retention system.

Description

technical field [0001] The invention belongs to the waste gas treatment technology of nuclear power plants, and in particular relates to a device for on-line vacuum drying and regeneration of detaining bed activated carbon of nuclear power units. Background technique [0002] The design function of the radioactive gas purification system of the nuclear power plant is to remove the radioactive inert gas in the waste gas treatment system of the nuclear power unit. The system is designed for direct discharge, receiving the exhaust of the hydrogen combustion system and the radioactive liquid storage tank, and the radioactive waste gas is adsorbed by the detaining bed activated carbon Finally, the sweeping gas and the remaining gas are discharged into the atmosphere through the chimney, and the stagnant bed is a key component of the system, and the performance of the activated carbon in it affects the radioactive level emitted by the system to the environment. [0003] The humidi...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): B01J20/34B01J20/20G21F9/02
CPCB01J20/3458B01J20/3416G21F9/02
Inventor 嵇永臣茆秋华张喜胜王成浩魏建军管玉峰周哲俊魏国军曹百通张晓宇高超王春阳
Owner JIANGSU NUCLEAR POWER CORP
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