CN105513662B - Nuclear power plant's radioactivity does treatment of wastes produced method - Google Patents

Nuclear power plant's radioactivity does treatment of wastes produced method Download PDF

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Publication number
CN105513662B
CN105513662B CN201510942568.XA CN201510942568A CN105513662B CN 105513662 B CN105513662 B CN 105513662B CN 201510942568 A CN201510942568 A CN 201510942568A CN 105513662 B CN105513662 B CN 105513662B
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radioactivity
power plant
nuclear power
filter
pyrolysis
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CN105513662A (en
Inventor
郑砚国
刘明章
王松平
李俊雄
邱乙亩
张旭
陶幼林
江文阳
周海洋
吴文凯
彭沛星
陆炜
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Peach Blossom River Hunan Nuclear Power Co Ltd
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Peach Blossom River Hunan Nuclear Power Co Ltd
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing
    • G21F9/32Processing by incineration
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/34Disposal of solid waste

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  • Engineering & Computer Science (AREA)
  • Environmental & Geological Engineering (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Processing Of Solid Wastes (AREA)

Abstract

Treatment of wastes produced method is done the invention discloses a kind of nuclear power plant's radioactivity of use vacuum pyrolysis method, it is characterized in that it includes (1) pre-processing:The dry waste of radioactivity is sorted, crushed;(2) it is pyrolyzed:To the dry waste pyrolysis of radioactivity in vacuum pyrolysis stove;(3) filter:Pyrolysis gas is filtered;(4) cement solidification:The completely reacted ash content of the dry waste of radioactivity is subjected to cement solidification process step;The present invention uses low-temperature vacuum themal dissociation, and method is reliable, and device is simple, easily realizes, the secondary waste of generation is less and will not produce the toxic and harmful gas such as dioxin, and volume reduction effect is close with burning, and pure cotton work clothes can reach 80:More than 1 volume reduction effect;The volume of the final radioactive solid waste of nuclear power plant is significantly reduced, the temporary pressure of nuclear power plant's radioactive solid waste temporary library is alleviated, greatly reduces the cost of radioactive solid waste final disposal, with good economy, the feature of environmental protection.

Description

Nuclear power plant's radioactivity does treatment of wastes produced method
Technical field
Treatment of wastes produced is done the present invention relates to a kind of nuclear power plant's radioactivity, specifically a kind of nuclear power plant's radioactivity is dry useless The processing method of thing, more particularly to a kind of nuclear power plant's radioactivity of use vacuum pyrolysis method does treatment of wastes produced method.
Background technology
Nuclear power station can be produced including work clothes, footware, paper, clothes, plastics, rubber etc. during operation, maintenance A large amount of compressible dry wastes of maintenance, its volume be 125m3/ unit year or so.Such waste will be passed into disuse after producing, but It is due to that it has radioactivity, wherein small part surface dose rate > 2mSv/h, to avoid the radionuclide included in waste The diffusion harm public and Environmental security to it, it is necessary to carry out reorganizing and outfit processing.According to national standard, nuclear power plant's radioactive solid waste Volume is no more than 50 m after processing3/ unit year, accordingly, it would be desirable to properly be located to nuclear power plant's radioactivity compactible waste Reason, to meet standard requirement.
At present, the compressible dry waste processing of existing nuclear power plant's radioactivity is main at home uses after cement solidification or compression Plus the tupe of cement solidification, the pattern has the following disadvantages.One is that cement solidification method uses a large amount of cement, is made after processing Solid waste volume not only not volume reduction increase-volume is larger on the contrary.Two be that cement solidification method uses inorganic body material solidification organism Material, radiolysis reaction can be occurred during by long-term storage by being proven firming body, and radiolysis gas can make firming body Rupture.Three be that compression adds cement solidification method because of the limitation of physical compression, is proven and also can only achieve not increase-volume also not The effect of volume reduction.Four be that compression adds cement solidification method because final solid waste volume is larger, and geological disposal is costly, to ring Border influence is larger.Five be compression plus cement solidification method inherently the characteristics of also determine needed for process equipment it is more, connect Mouth is complicated.
Also incineration treatment method is used, its technology maturation, volume reduction effect is obvious.But, two can be produced in burning process The toxic and harmful gas such as English are disliked, have certain influence on environment, in addition, the running temperature of incinerator is higher, maintenance cost is higher.
The content of the invention
Treatment of wastes produced method is done it is an object of the invention to provide a kind of nuclear power plant's radioactivity of use vacuum pyrolysis method.
The present invention, which is adopted the following technical scheme that, realizes its goal of the invention, and a kind of nuclear power plant's radioactivity does treatment of wastes produced Method, it comprises the following steps:
(1) pre-process:The dry waste of radioactivity is collected, and it is sorted, crushed;
The present invention step (1) in, the dry waste include during work clothes or footware or operation and maintenance produced by One or more in waste plastics, rubber.
(2) it is pyrolyzed:By step (1) pretreated dry waste input vacuum pyrolysis stove, furnace temperature is 300 DEG C~600 DEG C, vacuum Spend for -0.6pa~-0.9pa;Vacuum pyrolysis stove is vacuumized by hydraulic ejector;
Should be complete for pyrolysis hair, the present invention step (2) in, agitator is provided with vacuum pyrolysis stove.
The present invention step (2) in, preferably reaction condition is that furnace temperature is 380 DEG C~520 DEG C in vacuum pyrolysis stove.
(3) filter:Pyrolysis gas produced by vacuum pyrolysis stove pyrolytic reaction is filtered to remove by pipeline through fore filter Particulate matter in pyrolysis gas, then be passed through one end of U-shaped water pot and filter out soluble gas, the other end of U-shaped water pot is through high efficiency filter The suction inlet connection of device and hydraulic ejector, water pump one end is connected with water tank, the water inlet connection of the other end and hydraulic ejector, The jet of hydraulic ejector is connected with water tank, and insoluble gas is discharged through hydraulic ejector;
For by the heat derives of U-shaped water pot, the present invention step (3) in, U-shaped water pot is provided with external heat exchangers.
The present invention step (3) in, the filter core of the fore filter is non-woven fabrics or nylon wire or aluminium ripple net, is used for Filter the particulate matter of >=5 μm of particle diameters;The filter core of high efficiency particulate air filter is absorbent charcoal material.
For in real time detection tail gas, the present invention step (3) in, connect between high efficiency particulate air filter and the suction inlet of hydraulic ejector It is connected to tail gas on-line computing model.
For the vacuum in regulation vacuum pyrolysis stove, the present invention step (3) in, high efficiency particulate air filter and hydraulic ejector Flow control valve is connected between suction inlet;Water regulating valve is connected between water pump and the water inlet of hydraulic ejector.
(4) cement solidification:The ash content after dry waste in vacuum pyrolysis stove completely pyrolysis is carried out into cement from discharging opening export to consolidate Change is handled.
Due to using above-mentioned technical proposal, the present invention preferably realizes goal of the invention, using low-temperature vacuum themal dissociation, method Reliably, device is simple, easily realizes, the secondary waste of generation is less and will not produce the toxic and harmful gas such as dioxin, volume reduction Effect is close with burning, and pure cotton work clothes can reach 80:More than 1 volume reduction effect;Significantly reduce the final radioactivity of nuclear power plant The volume of solid waste, alleviates the temporary pressure of nuclear power plant's radioactive solid waste temporary library, greatly reduces radioactivity The cost of solid waste final disposal, with good economy, the feature of environmental protection.
Brief description of the drawings
Fig. 1 is the structural representation of the dry waste treatment equipment of radioactivity of the present invention.
Embodiment
Below in conjunction with the accompanying drawings and embodiment the invention will be further described.
As shown in Figure 1, a kind of nuclear power plant's radioactivity does treatment of wastes produced method, and it comprises the following steps:
(1) pre-process:The dry waste of radioactivity is collected, and it is sorted, crushed;
The present invention step (1) in, the dry waste include during work clothes or footware or operation and maintenance produced by One or more in waste plastics, rubber.
(2) it is pyrolyzed:By step, (1) pretreated dry waste puts into vacuum pyrolysis stove 1, and furnace temperature is 300 DEG C~600 DEG C, very Reciprocal of duty cycle is -0.6pa~-0.9pa;Vacuum pyrolysis stove 1 is vacuumized by hydraulic ejector 5;
Should be complete for pyrolysis hair, the present invention step (2) in, agitator 7 is provided with vacuum pyrolysis stove 1.
The present invention step (2) in, preferably reaction condition is that furnace temperature is 380 DEG C~520 DEG C in vacuum pyrolysis stove 1.
(3) filter:Pyrolysis gas produced by the pyrolytic reaction of vacuum pyrolysis stove 1 is crossed by pipeline through fore filter 2 to be filtered out The particulate matter gone in pyrolysis gas, then be passed through one end of U-shaped water pot 3 and filter out soluble gas, the other end of U-shaped water pot 3 is through efficient Filter 4 is connected with the suction inlet of hydraulic ejector 5, and the one end of water pump 9 is connected with water tank 6, and the other end enters with hydraulic ejector 5 The mouth of a river is connected, and the jet of hydraulic ejector 5 is connected with water tank 6, and insoluble gas is discharged through hydraulic ejector 5;
For by the heat derives of U-shaped water pot 3, the present invention step (3) in, U-shaped water pot is provided with external heat exchangers 4.
The present invention step (3) in, the filter core of the fore filter 2 is non-woven fabrics or nylon wire or aluminium ripple net, is used for Filter the particulate matter of >=5 μm of particle diameters;The filter core of high efficiency particulate air filter 4 is absorbent charcoal material.
For in real time detection tail gas, the present invention step (3) in, between the suction inlet of high efficiency particulate air filter 4 and hydraulic ejector 5 It is connected with tail gas on-line computing model 11.
For the vacuum in regulation vacuum pyrolysis stove 1, the present invention step (3) in, high efficiency particulate air filter 4 and hydraulic ejector 5 Suction inlet between be connected with flow control valve 8;Water regulating valve is connected between the water inlet of water pump 9 and hydraulic ejector 5 10。
(4) cement solidification:Ash content after dry waste in vacuum pyrolysis stove 1 completely pyrolysis is subjected to cement from discharging opening export Curing process.
The capacity of vacuum pyrolysis stove 1 of the present invention is 100L~800L, and the present embodiment is 100L;It is complete for reaction, throw every time The dry waste entered is 50 ﹪ of the heat size of vacuum pyrolysis stove 1 or so, and the filter core of fore filter 2 is aluminium ripple net, and high efficiency particulate air filter 4 is made For end filtration, its filter core is absorbent charcoal material, is mainly used in the particulate matter and radioactive substance of less than 0.5 μm of trapping;Efficiently Tail gas on-line computing model 11 and flow control valve 8 are connected between the suction inlet of filter 4 and hydraulic ejector 5.
During present invention work, sorted first to being collected into the temporary dry waste of radwaste building, can not be true The material of sky pyrolysis is sorted out(Predominantly metal material), then by can vacuum pyrolysis material carry out pulverization process;Crushing material The purpose one of processing is to prevent bulk materials are wrapped on agitator from causing agitator motor load larger;Two be to make material can be with React in the short period of time complete.The present embodiment is exemplified by handling cotton work clothes, in 100L vacuum pyrolysis stove 1, leads to Cross feeding mechanism 13 and add compressible dry wastes of 50 L by pretreatment in batches, vacuum pyrolysis stove 1 is warming up to 400 DEG C, In temperature-rise period, water pump 9 starts, and hydraulic ejector 5 works, and the vacuum in vacuum pyrolysis stove 1 is reached -0.7pa, and Work of knocking off makes the vacuum in the stove of vacuum pyrolysis stove 1 maintain -0.7pa or so;When temperature rises to more than 300 DEG C, pyrolysis Reaction starts, and the perseveration of agitator 7 makes material in stove react completely in stove, and the reaction time is 4 hours or so, vacuum pyrolysis stove Pyrolysis gas in 1 stove produced by material reaction is extracted with the work of hydraulic ejector 5, is first passed through pipeline and is entered preposition Filter 2, filters out the particulate matter of >=5 μm of particle diameters;Enter back into U-shaped water pot 3 to filter out the soluble gas in pyrolysis gas, together When, the temperature of pyrolysis gas is also reduced, the heating of U-shaped water pot 3 is exported by external heat exchangers 12;Then, into efficient mistake Filter 4 adsorbs the particulate matter not filtered out, and tail gas on-line computing model 11 can monitor the emission behaviour of tail gas;Last tail gas passes through waterpower Injector 5 is discharged, and the water feeding water tank 6 that the jet of hydraulic ejector 5 sprays is recycled;Ash after the pyrolysis completely of dry waste Point(Main component is carbon molecules)It is deposited in the stove of vacuum pyrolysis stove 1, is discharged by discharging opening, is carried out after collection at cement solidification Reason.By regulating pondage regulating valve 10 and the size of regulation flow control valve 8, the vacuum that can adjust in vacuum pyrolysis stove 1 is big It is small, it is also used for test system parameter in debugging and maintenance process.Water in water tank 6 needs timely benefit after natural evaporation and consumption Water.
To ensure filter effect, the filter core of fore filter 2 is handling 900 m3~1200 m3Carried out after material at replacing Reason, the filter core of high efficiency particulate air filter 4 is handling 2200 m3~2500 m3Replacing processing is carried out after material, the filter core changed can be with doing Waste reacted ash content completely carries out cement solidification processing together.
The inventive method is feasible, and device is simple, easily realizes, the secondary waste of generation is less and will not produce dioxin etc. Toxic and harmful gas, volume reduction effect is close with burning, and 80 are can reach to pure cotton work clothes:More than 1 volume reduction effect;Significantly reduce The volume of the final radioactive solid waste of nuclear power plant, alleviates the temporary pressure of nuclear power plant's radioactive solid waste temporary library, The cost of radioactive solid waste final disposal is greatly reduced, with good economy, the feature of environmental protection.

Claims (6)

1. a kind of nuclear power plant's radioactivity does treatment of wastes produced method, it is characterized in that it comprises the following steps:
(1) pre-process:The dry waste of radioactivity is collected, and it is sorted, crushed;
Step (1) in, the dry waste include during work clothes or footware or operation and maintenance produced by waste plastics, rubber One or more in glue;
(2) it is pyrolyzed:By step (1) pretreated dry waste input vacuum pyrolysis stove, furnace temperature is 300 DEG C~600 DEG C, vacuum For -0.6pa~-0.9pa;Vacuum pyrolysis stove is vacuumized by hydraulic ejector;
(3) filter:Pyrolysis gas produced by vacuum pyrolysis stove pyrolytic reaction is filtered to remove pyrolysis by pipeline through fore filter Particulate matter in gas, then be passed through one end of U-shaped water pot and filter out soluble gas, the other end of U-shaped water pot through high efficiency particulate air filter with The suction inlet connection of hydraulic ejector, water pump one end is connected with water tank, the water inlet connection of the other end and hydraulic ejector, waterpower The jet of injector is connected with water tank, and insoluble gas is discharged through hydraulic ejector;
Step (3) in, the filter core of the fore filter is non-woven fabrics or nylon wire or aluminium ripple net, for filtering >=5 μm of particle diameters Particulate matter;The filter core of high efficiency particulate air filter is absorbent charcoal material;
(4) cement solidification:Ash content after dry waste in vacuum pyrolysis stove completely pyrolysis is carried out at cement solidification from discharging opening export Reason.
2. nuclear power plant's radioactivity does treatment of wastes produced method according to claim 1, it is characterized in that step (2) in, Vacuum Heat Solve and agitator is provided with stove.
3. nuclear power plant's radioactivity does treatment of wastes produced method according to claim 1, it is characterized in that step (2) in, Vacuum Heat It is that furnace temperature is 380 DEG C~520 DEG C to solve preferably reaction condition in stove.
4. nuclear power plant's radioactivity does treatment of wastes produced method according to claim 1, it is characterized in that step (3) in, U-shaped water Tank is provided with external heat exchangers.
5. nuclear power plant's radioactivity does treatment of wastes produced method according to claim 1, it is characterized in that step (3) in, efficient mistake Tail gas on-line computing model is connected between filter and the suction inlet of hydraulic ejector.
6. nuclear power plant's radioactivity does treatment of wastes produced method according to claim 1, it is characterized in that step (3) in, efficient mistake Flow control valve is connected between filter and the suction inlet of hydraulic ejector;Connected between water pump and the water inlet of hydraulic ejector There is water regulating valve.
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CN107044945B (en) * 2016-10-17 2020-12-25 上海核工程研究设计院 Vacuum drying test method for ion exchange resin
CN106782731A (en) * 2016-12-30 2017-05-31 天津梦之岛科技有限公司 A kind of Radwastes treatment sorting arrangement
CN108630335A (en) * 2018-03-13 2018-10-09 中国核电工程有限公司 Vacuum microwave drying system and drying means in a kind of radioactivity wet type pail for used dressings

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JPS63298197A (en) * 1987-05-29 1988-12-05 Nippon Atom Ind Group Co Ltd Treatment of radioactive oil containing waste
JP5651433B2 (en) * 2010-11-11 2015-01-14 株式会社東芝 Waste ion exchange resin treatment method and treatment apparatus
CN202034076U (en) * 2011-03-30 2011-11-09 西北核技术研究所 Radioactive-waste treatment system
JP2013096896A (en) * 2011-11-02 2013-05-20 Toshiba Corp Method and apparatus for treating boric acid containing waste fluid
JP2014098637A (en) * 2012-11-14 2014-05-29 Toshiba Corp Method and device for treating radioactive waste solution

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