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In-barrel vacuum microwave drying system and method for radioactive wet wastes

A vacuum microwave drying and drying system technology, used in radioactive purification, garbage drying, sludge drying, etc., can solve the problems of increased disposal costs, large capacity expansion ratio, and non-compliance with the principle of minimizing radioactive waste. , The heating temperature is uniform, which is conducive to the effect of water evaporation

Inactive Publication Date: 2018-10-09
CHINA NUCLEAR POWER ENG CO LTD
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Problems solved by technology

Among them, precipitation, adsorption, ion exchange and membrane treatment technologies are mainly aimed at radioactive waste liquid containing specific substances, so the scope of application is limited; although evaporation and concentration technology has a wide range of applications, the distillation residue produced by concentration still needs further treatment; cement Although solidification technology has the advantages of low price, safety and reliability, it is widely used in the solidification and conditioning of radioactive waste, but the technology has a large capacity expansion ratio (usually between 2-3), which neither conforms to the principle of radioactive waste minimization, nor makes it Disposal costs increase

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  • In-barrel vacuum microwave drying system and method for radioactive wet wastes

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Embodiment Construction

[0032] The specific implementation manners of the present invention will be further described below in conjunction with the accompanying drawings.

[0033] The composition of the vacuum microwave drying system in the exemplary radioactive wet waste bucket of the present invention is as follows: figure 1 As shown, it includes a pretreatment part (also includes a pretreatment device 1, a first delivery pump 12), a microwave vacuum drying part in a barrel (also includes a drying barrel 2 placed in a drying station), an exhaust gas purification and condensation treatment part (also includes Demister 3, filter 4, first condenser 5, steam-water separator 6, first condensate storage tank 7, second condensate storage tank 8, vacuum pump 9, non-condensable gas storage tank 10, second condenser 11. The second delivery pump 13, the third delivery pump 14, the fourth delivery pump 15, the adsorption filter 16), the monitoring analysis part (also includes the tail gas continuous monitoring...

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Abstract

The invention belongs to the technical field of radioactive waste treatment and relates to an in-barrel vacuum microwave drying system and method for radioactive wet wastes. The drying system comprises a drying barrel, a demister, a filter, a condenser, a steam-water separator, a vacuum pump, a tail gas continuous monitoring device and connecting pipelines; the drying barrel is used for drying thewastes by microwave heating; the demister, the filter, the condenser, the steam-water separator and the vacuum pump which are connected in sequence are respectively used for realizing demisting, filtration, condensation, steam-water separation and vacuumizing treatment of evaporated tail gases generated by drying; and the tail gas continuous monitoring device is connected with the condenser and is used for monitoring noncondensable gases in the evaporated tail gases and discharging qualified noncondensable gases into the air by the connecting pipeline connected with an outlet of the tail gascontinuous monitoring device. By using the drying system and method disclosed by the invention, the rapid drying of various radioactive wastes can be realized, new substances are not introduced in a drying process, and the tail gases discharged after being dried almost have no any harmful effects on the environment.

Description

technical field [0001] The invention belongs to the technical field of radioactive waste treatment, and relates to a vacuum microwave drying system and a drying method in a radioactive wet waste barrel. Background technique [0002] With the continuous application of nuclear technology, the problem of temporary storage, treatment and disposal of radioactive waste has become more and more prominent, especially most radioactive waste does not meet the requirement that the free water content is less than 1% without treatment. [0003] At present, the treatment technologies for reducing the free water content of radioactive wet waste include precipitation, adsorption (including silica gel adsorption), ion exchange, membrane treatment, evaporative concentration, cement solidification, and drying in barrels. Among them, precipitation, adsorption, ion exchange and membrane treatment technologies are mainly aimed at radioactive waste liquid containing specific substances, so the sco...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/00G21F9/02G21F9/06G21F9/20G21F9/30G21F9/34F26B1/00F26B5/04F26B25/00
CPCF26B1/00F26B5/048F26B25/005F26B25/006F26B25/007F26B2200/04F26B2200/18G21F9/008G21F9/02G21F9/06G21F9/20G21F9/30G21F9/34
Inventor 宫本希王沾祺苗顺占李绍媛董慧民蒋涛李芳林王永辉黄永锋胡有坤
Owner CHINA NUCLEAR POWER ENG CO LTD
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