CN105513662A - Method for treating dry radioactive waste of nuclear power plant - Google Patents
Method for treating dry radioactive waste of nuclear power plant Download PDFInfo
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- CN105513662A CN105513662A CN201510942568.XA CN201510942568A CN105513662A CN 105513662 A CN105513662 A CN 105513662A CN 201510942568 A CN201510942568 A CN 201510942568A CN 105513662 A CN105513662 A CN 105513662A
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- power plant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
- G21F9/32—Processing by incineration
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal 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
The invention discloses a method for treating dry radioactive waste of a nuclear power plant by adopting a vacuum pyrolysis method. The method is characterized by comprising steps as follows: (1), pretreatment: the dry radioactive waste is subjected to sorting and grinding; (2), pyrolysis: the dry radioactive waste is subjected to pyrolysis in a vacuum pyrolysis furnace; (3), filtering: pyrolysis gas is filtered; (4), cement solidification: ash obtained after complete reaction of the dry radioactive waste is subjected to cement solidification treatment. The method for treating the dry radioactive waste of the nuclear power plant adopts low-temperature vacuum pyrolysis and is reliable and easy to implement, equipment is simple, less secondary waste is produced, toxic and harmful gas such as dioxin and the like cannot be produced, the volume reduction effect is similar to that of incineration, and the volume reduction effect on pure cotton work clothes can be higher than 80:1; the volume of the final radioactive solid waste of the nuclear power plant is remarkably reduced, the temporary storage pressure of a radioactive solid waste temporary storage depository is relieved, the final treatment cost of the radioactive solid waste is greatly reduced, and the method has good economic efficiency and environmental protection property.
Description
Technical field
The present invention relates to a kind of nuclear power plant radioactivity and do treatment of wastes produced, specifically a kind of nuclear power plant radioactivity does treatment of wastes produced method, particularly relates to a kind of nuclear power plant's radioactivity of vacuum pyrolysis method that adopts and does treatment of wastes produced method.
Background technology
Nuclear power station is between operation, turn(a)round, and can produce the dry refuse of a large amount of compressible maintenance comprising working cloth, footware, paper, clothes, plastics, rubber etc., its volume is 125m
3about/unit year.This type of refuse will be passed into disuse after producing, but because it has radioactivity, wherein small part surface dose rate > 2mSv/h, for avoiding the radioactive nuclide diffusion comprised in refuse to endanger the public and Environmental security, needs to reorganize and outfit process to it.According to national standard, nuclear power plant's radioactive solid waste volume is for being not more than 50m after process
3in/unit year, therefore, need to deal carefully with nuclear power plant's radioactivity compactible waste, to meet standard-required.
At present, the compressible dry refuse process of existing nuclear power plant radioactivity adds the tupe of cement solidification after mainly adopting cement solidification or compression at home, this pattern exists following shortcoming.One is that cement solidification method uses a large amount of cement, the solid waste volume after process is not only subtracted hold increase-volume on the contrary larger.Two is that cement solidification method uses inorganic body material cured organism material, and be proven firming body and radiolysis reaction can occur in long-term storage process, radiolysis gas can make firming body break.Three is that compression adds the limitation of cement solidification method because of physical compression, is proven and also can only reaches the effect that not increase-volume does not subtract appearance yet.Four be compression add cement solidification method because of final solid waste volume comparatively large, geological disposal costly, has greater environmental impacts.Five is that compression adds cement solidification method feature inherently to also determine required process equipment more, complex interfaces.
Also there is employing incineration treatment method, its technology maturation, subtract appearance successful.But can produce the toxic and harmfuls such as dioxin in burning process, have certain influence to environment, in addition, the running temperature of incinerator is higher, and maintenance cost is higher.
Summary of the invention
The object of this invention is to provide a kind of nuclear power plant's radioactivity of vacuum pyrolysis method that adopts and do treatment of wastes produced method.
The present invention adopts following technical scheme to realize its goal of the invention, and a kind of nuclear power plant radioactivity does treatment of wastes produced method, and it comprises the following steps:
(1) pre-service: collect radioactivity dry refuse, and it is sorted, pulverize;
The present invention step (1) in, described dry refuse comprise in working cloth or footware or operation and the waste plastics produced between turn(a)round, rubber one or more.
(2) pyrolysis: by step (1) pretreated dry refuse input vacuum pyrolysis stove, furnace temperature is 300 DEG C ~ 600 DEG C, and vacuum tightness is-0.6pa ~-0.9pa; Vacuum pyrolysis stove is vacuumized by hydraulic ejector;
Sending out for pyrolysis should be complete, the present invention step (2) in, be provided with stirrer in vacuum pyrolysis stove.
The present invention step (2) in, in vacuum pyrolysis stove, preferably reaction conditions is furnace temperature is 380 DEG C ~ 520 DEG C.
(3) filter: the pyrolysis gas that vacuum pyrolysis stove pyrolytic reaction produces is by the particle of pipeline in preposition metre filter removing pyrolysis gas, pass into one end filtering soluble gas of U-shaped water pot again, the other end of U-shaped water pot is connected with the suction inlet of hydraulic ejector through high efficiency particulate air filter, water pump one end is connected with water tank, the other end is connected with the water inlet of hydraulic ejector, the injection orifice of hydraulic ejector is connected with water tank, and soluble gas is discharged through hydraulic ejector;
For by the heat of U-shaped water pot derive, 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 described fore filter is nonwoven fabrics or nylon wire or aluminium ripple net, for filtering >=particle of 5 μm of particle diameters; The filter core of high efficiency particulate air filter is absorbent charcoal material.
For detecting tail gas in real time, the present invention step (3) in, be connected with tail gas on-line computing model between high efficiency particulate air filter and the suction inlet of hydraulic ejector.
For regulating the vacuum tightness in vacuum pyrolysis stove, the present invention step (3) in, be connected with flow control valve between high efficiency particulate air filter and the suction inlet of hydraulic ejector; Water regulating valve is connected with between water pump and the water inlet of hydraulic ejector.
(4) cement solidification: the ash content after the complete pyrolysis of refuse dry in vacuum pyrolysis stove is derived from discharging opening and carries out cement solidification process.
Owing to adopting technique scheme, the present invention achieves goal of the invention preferably, adopt low-temperature vacuum themal dissociation, method is reliable, device is simple, easily realizes, and the secondary refuse of generation is less and can not produce the toxic and harmfuls such as dioxin, subtract and hold effect and burn close, what textile working cloth can reach more than 80:1 subtracts appearance effect; Significantly reduce the volume of the final radioactive solid waste of nuclear power plant, alleviate the temporary pressure of nuclear power plant's radioactive solid waste temporary library, greatly reduce the cost of radioactive solid waste final disposal, there is good economy, the feature of environmental protection.
Accompanying drawing explanation
Fig. 1 is the structural representation of the dry waste treatment equipment of radioactivity of the present invention.
Embodiment
Below in conjunction with drawings and Examples, the invention will be further described.
As shown in Figure 1, a kind of nuclear power plant radioactivity does treatment of wastes produced method, and it comprises the following steps:
(1) pre-service: collect radioactivity dry refuse, and it is sorted, pulverize;
The present invention step (1) in, described dry refuse comprise in working cloth or footware or operation and the waste plastics produced between turn(a)round, rubber one or more.
(2) pyrolysis: by step (1) pretreated dry refuse input vacuum pyrolysis stove 1, furnace temperature is 300 DEG C ~ 600 DEG C, and vacuum tightness is-0.6pa ~-0.9pa; Vacuum pyrolysis stove 1 is vacuumized by hydraulic ejector 5;
Sending out for pyrolysis should be complete, the present invention step (2) in, be provided with stirrer 7 in vacuum pyrolysis stove 1.
The present invention step (2) in, in vacuum pyrolysis stove 1, preferably reaction conditions is furnace temperature is 380 DEG C ~ 520 DEG C.
(3) filter: the pyrolysis gas that vacuum pyrolysis stove 1 pyrolytic reaction produces crosses the particle filtered in pyrolysis gas through fore filter 2 by pipeline, pass into one end filtering soluble gas of U-shaped water pot 3 again, the other end of U-shaped water pot 3 is connected through the suction inlet of high efficiency particulate air filter 4 with hydraulic ejector 5, water pump 9 one end is connected with water tank 6, the other end is connected with the water inlet of hydraulic ejector 5, the injection orifice of hydraulic ejector 5 is connected with water tank 6, and soluble gas is discharged through hydraulic ejector 5;
For by the heat of U-shaped water pot 3 derive, 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 described fore filter 2 is nonwoven fabrics or nylon wire or aluminium ripple net, for filtering >=particle of 5 μm of particle diameters; The filter core of high efficiency particulate air filter 4 is absorbent charcoal material.
For detecting tail gas in real time, the present invention step (3) in, be connected with tail gas on-line computing model 11 between the suction inlet of high efficiency particulate air filter 4 and hydraulic ejector 5.
For regulating the vacuum tightness in vacuum pyrolysis stove 1, the present invention step (3) in, be connected with flow control valve 8 between the suction inlet of high efficiency particulate air filter 4 and hydraulic ejector 5; Water regulating valve 10 is connected with between the water inlet of water pump 9 and hydraulic ejector 5.
(4) cement solidification: the ash content after the complete pyrolysis of refuse dry in vacuum pyrolysis stove 1 is derived from discharging opening and carries out cement solidification process.
The capacity of vacuum pyrolysis stove 1 of the present invention is 100L ~ 800L, and the present embodiment is 100L; For reacting completely, the dry refuse of each input is about 50 ﹪ of vacuum pyrolysis stove 1 heat size, and the filter core of fore filter 2 is aluminium ripple net, and high efficiency particulate air filter 4 is as end filtration, its filter core is absorbent charcoal material, is mainly used in particle and the radiomaterial of trapping less than 0.5 μm; Tail gas on-line computing model 11 and flow control valve 8 is connected with between the suction inlet of high efficiency particulate air filter 4 and hydraulic ejector 5.
When the present invention works, first the dry refuse collecting radwaste building temporary is sorted, can not the material of vacuum pyrolysis sort out (being mainly metal material), then the material of vacuum pyrolysis can carry out pulverization process; The object one of crushing material process prevents from bulk materials to be wrapped on stirrer to cause agitator motor load larger; Two is that material can be reacted completely in the short period of time.The present embodiment is to process cotton working cloth, in the vacuum pyrolysis stove 1 of 100L, 50L is added in batches through pretreated compressible dry refuse by feeding mechanism 13, vacuum pyrolysis stove 1 is warming up to 400 DEG C, in temperature-rise period, water pump 9 starts, and hydraulic ejector 5 works, make the vacuum tightness in vacuum pyrolysis stove 1 reach-0.7pa, and discontinuous operation make the vacuum tightness in vacuum pyrolysis stove 1 stove maintain about-0.7pa; When temperature rises to more than 300 DEG C, pyrolytic reaction starts, in stove, stirrer 7 perseveration makes material complete reaction in stove, reaction time is 4 hours, the pyrolysis gas that in vacuum pyrolysis stove 1 stove, material reaction produces is drawn out of along with the work of hydraulic ejector 5, first enter fore filter 2 by pipeline, filter the particle of filtering >=5 μm particle diameter; Enter U-shaped water pot 3 again by the soluble gas filtering in pyrolysis gas, meanwhile, also reduce the temperature of pyrolysis gas, the intensification of U-shaped water pot 3 is derived by external heat exchangers 12; Then, enter the particle that high efficiency particulate air filter 4 adsorbs non-filtering, tail gas on-line computing model 11 can monitor the emission behaviour of tail gas; Last tail gas is discharged by hydraulic ejector 5, and the water of the injection orifice ejection of hydraulic ejector 5 is sent into water tank 6 and recycled; Ash content (principal ingredient is carbon molecule) after the complete pyrolysis of dry refuse is deposited in vacuum pyrolysis stove 1 stove, is discharged, carry out cement solidification process after collection by discharging opening.By the size of regulating pondage variable valve 10 and adjust flux variable valve 8, the vacuum tightness size in adjustable vacuum pyrolysis stove 1, also for test macro parameter in debugging and maintenance process.Water in water tank 6 needs timely moisturizing in spontaneous evaporation and after consuming.
For ensureing filter effect, the filter core of fore filter 2 is at process 900m
3~ 1200m
3carry out replacing process after material, the filter core of high efficiency particulate air filter 4 is at process 2200m
3~ 2500m
3carry out replacing process after material, the filter core changed can carry out cement solidification process together with the ash content after dry refuse complete reaction.
The inventive method is feasible, and device is simple, easily realizes, and the secondary refuse of generation is less and can not produce the toxic and harmfuls such as dioxin, subtracts to hold effect and burn close, and what can reach more than 80:1 to textile working cloth subtracts appearance effect; Significantly reduce the volume of the final radioactive solid waste of nuclear power plant, alleviate the temporary pressure of nuclear power plant's radioactive solid waste temporary library, greatly reduce the cost of radioactive solid waste final disposal, there is good economy, the feature of environmental protection.
Claims (8)
1. nuclear power plant's radioactivity does a treatment of wastes produced method, it is characterized in that it comprises the following steps:
(1) pre-service: collect radioactivity dry refuse, and it is sorted, pulverize;
(2) pyrolysis: by step (1) pretreated dry refuse input vacuum pyrolysis stove, furnace temperature is 300 DEG C ~ 600 DEG C, and vacuum tightness is-0.6pa ~-0.9pa; Vacuum pyrolysis stove is vacuumized by hydraulic ejector;
(3) filter: the pyrolysis gas that vacuum pyrolysis stove pyrolytic reaction produces is by the particle of pipeline in preposition metre filter removing pyrolysis gas, pass into one end filtering soluble gas of U-shaped water pot again, the other end of U-shaped water pot is connected with the suction inlet of hydraulic ejector through high efficiency particulate air filter, water pump one end is connected with water tank, the other end is connected with the water inlet of hydraulic ejector, the injection orifice of hydraulic ejector is connected with water tank, and soluble gas is discharged through hydraulic ejector;
(4) cement solidification: the ash content after the complete pyrolysis of refuse dry in vacuum pyrolysis stove is derived from discharging opening and carries out cement solidification process.
2. nuclear power plant's radioactivity does treatment of wastes produced method according to claim 1, it is characterized in that step (2) in, be provided with stirrer in vacuum pyrolysis 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, in vacuum pyrolysis stove, preferably reaction conditions is furnace temperature is 380 DEG C ~ 520 DEG C.
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 pot 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, the filter core of described fore filter is nonwoven fabrics or nylon wire or aluminium ripple net, for filtering >=particle of 5 μm of particle diameters; The filter core of high efficiency particulate air filter is absorbent charcoal material.
6. nuclear power plant's radioactivity does treatment of wastes produced method according to claim 1, it is characterized in that step (3) in, be connected with tail gas on-line computing model between high efficiency particulate air filter and the suction inlet of hydraulic ejector.
7. nuclear power plant's radioactivity does treatment of wastes produced method according to claim 1, it is characterized in that step (3) in, be connected with flow control valve between high efficiency particulate air filter and the suction inlet of hydraulic ejector; Water regulating valve is connected with between water pump and the water inlet of hydraulic ejector.
8. according to claim 1 or 2 or 3 or 4 or 5 or 6 or 7, nuclear power plant's radioactivity does treatment of wastes produced method, it is characterized in that step (1) in, described dry refuse comprise in working cloth or footware or operation and the waste plastics produced between turn(a)round, rubber one or more.
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
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| 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 |
| CN107044945A (en) * | 2016-10-17 | 2017-08-15 | 上海核工程研究设计院 | A kind of ion exchange resin vacuum drying test method and device |
| 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 |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107044945A (en) * | 2016-10-17 | 2017-08-15 | 上海核工程研究设计院 | A kind of ion exchange resin vacuum drying test method and device |
| 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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| CN105513662B (en) | 2017-08-25 |
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