CN102201271A - System for processing radioactive wastes - Google Patents
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- CN102201271A CN102201271A CN2011100783972A CN201110078397A CN102201271A CN 102201271 A CN102201271 A CN 102201271A CN 2011100783972 A CN2011100783972 A CN 2011100783972A CN 201110078397 A CN201110078397 A CN 201110078397A CN 102201271 A CN102201271 A CN 102201271A
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- radioactive waste
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Abstract
The invention relates to a system for processing radioactive wastes, which is integrated in a movable shelter including a volume-reduction device and a tail-gas processor connected to a pipeline of the volume-reduction device; and both the volume-reduction device and the tail-gas processor are placed in a vacuum environment. The invention provides a movable system for processing radioactive wastes, which reduces storage space, causes little pollution to the environment and is low in storage cost.
Description
Technical field
The present invention relates to the disposal system of a kind of nuclear industry and nuclear power station discarded object, relate in particular to a kind of disposal system that contains radioactive waste.
Background technology
Nuclear power is subject to people's attention day by day and utilizes as a kind of energy efficient, cleaning, and by 2010, China mainland just had 13 nuclear power generating sets putting into effect, also will successively drop into commercial operation at 24 units building.Nuclear power is when bringing the tremendous economic interests to people, manufacturability refuse and technical refuse that it produces in the course of the work all have certain specific radioactivity, can deposit after must handling through certain technical measures, if it is improper to handle or deposit, the radioactive contamination that causes when suffering nature such as earthquake, the attack of terrorism for example or artificial destruction will be to the consequence of bringing on a disaster property of people.When at present these being contained radioactive waste and handle, adopt cement solidification often or burn mode such as filtration.For the cement solidification mode, contain active discarded object directly after overcompression, the water mudding is deposited, because of its increase-volume than big, storage expenses is high, take storage space is subjected to various challenges greatly.For burning filter type, through burning and filter to containing radioactive waste, though can alleviate storage space to a great extent, the also corresponding reduction of storage expenses, but owing to the pollution of its burning generation bioxin to environment also can not look down upon, simultaneously, present this burning mode structure is very huge, except that investment intensity greatly, its stationary structure has brought each power station to contain radioactive waste and has had to be transferred to the drawback that subtracts the processing of appearance processing enter, increased the possibility that nucleic looses virtually outward, and because the restriction of type of heating, make the nucleic in the radioactive waste when burning, form gasoloid, when increasing the vent gas treatment difficulty, also increased input and the pressure handled, might further cause secondary or repeated pollution with the thermal current drift.
These different modes subtract the appearance processing to reduce storage expenses to having radioactive nuclear waste, reduce storage, keeping and social pressures, subtract in the appearance process at radioactive waste, if the radioactive nuclide in the refuse is dealt with improperly, will bring the pollution of environment and to the injury of human body, even in daily municipal waste is handled, burning generation De bioxin also can not look down upon to the pollution of environment.
Summary of the invention
In order to solve the above-mentioned technical matters that exists in the background technology, the invention provides a kind of storage space, environmental pollution is little and storage expenses is low packaged type disposal system that contains radioactive waste of reducing.
Technical solution of the present invention is: the invention provides a kind ofly to containing the packaged type disposal system of radioactive waste, its special character is: the described disposal system that contains radioactive waste is integrated in a packaged type, comprise capacity-reduction device and the shield of the exhaust gas processing device that links to each other with the capacity-reduction device pipeline in; Described capacity-reduction device and exhaust gas processing device are co-located in the vacuum environment.
Above-mentioned exhaust gas processing device comprises cold-trap and the filtration unit that links to each other with the cold-trap pipeline, and described capacity-reduction device, cold-trap and filtration unit link to each other by pipeline successively.
Above-mentioned filtration unit comprises first filtrator, condenser and second filtrator; Described cold-trap inserts first filtrator; Described first filtrator inserts second filtrator by condenser; Described condenser inserts cold-trap; Described second filtrator is an active carbon filter.
Above-mentioned capacity-reduction device comprises setting-out evaporation or carbonizing plant and coupled sample input end; Described sample input end inserts cold-trap by setting-out evaporation or carbonizing plant.
Above-mentioned setting-out evaporation or carbonizing plant comprise storage barrel, are arranged at the microwave heating unit and the temperature measuring equipment of storage barrel outside.
Above-mentioned temperature measuring equipment is infrared temperature-test sensor, contactless material temperature probe or contact material temperature probe.
Above-mentioned sample input end is solid-state castoff input end or liquid waste input end.
Advantage of the present invention is:
The invention provides a kind of to containing the disposal system of radioactive waste, this system utilizes microwave heating to have penetration capacity is strong and the replacement of volume-heated characteristics is adopted electricity, oil, vapours or Infrared Heating mode abroad in the radioactive waste dry run, realized setting-out evaporation technique means, avoided removing
137Cs,
134The boiling of water was to radioactive nuclide and aerocolloidal taking out of when other nucleic was owing to heating outside the Cs; Utilize microwave to have selectivity heating and the little characteristics of thermal inertia, effectively will remove by computer close-loop control
137Cs,
134Other nucleic that Cs is outer is with bioxin has been controlled at its turning point following (temperature control), thus the generation of effectively having avoided the silt of other nucleic from refuse to go out the He bioxin; The shell and tube cold-trap can will contain
137Cs,
134The aerocolloidal hot gas of Cs dropped to temperature below 17 ℃ from 120 ℃ within 0.5 to 1.5 minute rapidly, had realized that this technological process has the technical measures of regulating tail gas and raffinate pH value simultaneously to the holding back of nucleic; Examine the combination of level high efficiency particulate air filter, active carbon filter and condenser, can guarantee the qualified discharge of tail gas and raffinate.The present invention relates to adopt a kind of group technology to subtract in the appearance process new technology that radioactive nuclide and harmful element bioxin are controlled, particularly in the radioactive waste at radioactive waste
90Sr,
137Cs,
134Cs,
60Co,
238Pu,
241Control technology and technology that Am and flammable nuclear waste carbonization process Zhong bioxin generate have and reduce storage space, environmental pollution is little and storage expenses is low advantage.
Description of drawings
Fig. 1 is the radioactive waste disposal system structural representation that contains provided by the present invention.
Embodiment
Referring to Fig. 1, the invention provides a kind of disposal system that contains radioactive waste, this system is according to various nucleic and material is survived or generation all has certain condition to carry out, as 17.53 half life period
90Sr, 770 ℃ of molten points, 1382 ℃ of boiling points, 30 years half life period
137Cs, 28.44 ℃ of molten points, 671 ℃ of boiling points, 2.062 half life period
134Cs, 28.4 ℃ of molten points, 678.4 ℃ of boiling points, 5.26 half life period
60Co, 1495 ℃ of molten points, 2927 ℃ of boiling points, 87.8 half life period
238Pu, 640 ℃ of molten points, 3234 ℃ of boiling points, 458 years half life period
241Am, 994 ℃ of molten points, 2607 ℃ of boiling points.And be colorless and odorless solid matter bioxin under standard state, fusing point is 303～305 ℃, and its half life period in soil reaches 9～12 years, and the half life period in the mankind and animal body is 5～10 years, and average out to is about 7 years.It is highly stable below 705 ℃, and is non-volatile under the normal temperature, is difficult to oxidation, decomposition or hydrolysis.Under 300～500 ℃ temperature, the carbon monoxide and the carbon dioxide of few part are converted into aliphatic precursor under the effect of catalyzer.If there is aluminium oxide to exist, catalytic reaction can also take place in the aliphatics precursor, generate aromatic precursor, chlorination takes place again and produces the aromatic series precursor in aromatics, and these precursors do at transition metal (mainly being copper) that reaction generates bioxin under the condition of catalyzer at last.
System provided by the present invention comprises capacity-reduction device and the exhaust gas processing device that links to each other with the capacity-reduction device pipeline; Capacity-reduction device and exhaust gas processing device are co-located in the vacuum environment; Exhaust gas processing device comprises cold-trap 3 and the filtration unit that links to each other with cold-trap 3 pipelines, and capacity-reduction device, cold-trap 3 and filtration unit link to each other by pipeline successively.
Filtration unit comprises filtrator 4, condenser 5 and active carbon filter 6; Cold-trap 3 inserts filtrator 4; Filtrator 4 inserts active carbon filter 6 by condenser 5; Condenser 5 inserts cold-trap 3.
Capacity-reduction device comprises setting-out evaporation or carbonizing plant 2 and coupled sample input end; The sample input end inserts cold-trap 3 by setting-out evaporation or carbonizing plant 2; Setting-out evaporation or carbonizing plant 2 comprise storage barrel, are arranged at the microwave heating unit and the temperature measuring equipment of storage barrel outside; Temperature measuring equipment is infrared temperature-test sensor, contactless material temperature probe or contact material temperature probe.
The sample input end is solid-state castoff input end or liquid waste input end.
Principle of work of the present invention is:
To contain radioactive waste and carry out its purpose of heat treated and dewater exactly or carbonization, obtain containing the hot gas of indivedual nucleic and the solid-state castoff two parts after the carbonization; Can handle solid-state or liquid, use very convenient, if handle to as if solid-state, directly carry out drying and carbonization treatment, if handle to as if liquid, then directly dewater and dried; Directly use " high whole nuclear waste disposal container " (ZL 2,010 2 0301564.6) or cement to seal up for safekeeping through the solid-state castoff after the carbonization; To contain radioactive waste heats, this type of heating can be electrical heating, oil heating, vapours heating, Infrared Heating or microwave heating, preferred microwave heating, and, can also carry out temperature control to heating process, make to obtain containing the hot gas of indivedual nucleic and the solid-state castoff after the carbonization, realize that temperature controlled purpose is exactly the generation that storage is stayed most of nucleic and suppressed bioxin, effectively will remove by computer close-loop control
137Cs,
134Other nucleic that Cs is outer is with bioxin has been controlled at its turning point following (temperature control), thus the generation of effectively having avoided the silt of other nucleic from refuse to go out the He bioxin; The hot gas that contains the indivedual nucleic of trace that produces after the microwave heating is carried out the chilling extraction, and such step is unexistent at present, is different with prior art, is one of the most basic inventive point.The condition of chilling extraction can be for example to drop to rapidly below 17 ℃ from 120 ℃ in the temperature of the hot gas that will contain indivedual nucleic within 0.5min～1.5min, perhaps the temperature of hot gas is reduced to radioactive nuclide at short notice, for example below the fusing point of caesium, such purpose, be different from the filtration of existing step, contain radioactive nuclide after the process heating, tending to form gasoloid spreads with hot gas, iff filtering, not only increased the pressure of vent gas treatment, simultaneously unavoidable some nucleic further is discharged from, the secondary or the repeated pollution that cause radiomaterial worsen environment.This technological means that extracts the present invention's microwave heating---chilling will contain the gasoloid of indivedual radioactive nuclides under the condition of temperature quenching, directly be stranded in the liquid coolant, can effectively avoid containing the gasoloid contaminated environment of nucleic.Meanwhile, the present invention has increased the step that the gas that contains nucleic is filtered, and this filtration can be an one or many, and it is best generally getting 2-3 effect, and cleaning of off-gas makes it up to standard so more completely.The mode of this filtration is activated carbon filtration or carbon fiber filter type.
As another unique distinction of the present invention is that packaged type shield structure can be handled on the spot with the refuse of finishing on the spot different nuclear powers base, and it also can be used for other nuclear industry and nuclear application certainly.This disposal route that contains radioactive waste provided by the present invention carries out in vacuum environment, avoided the radioactive waste transhipment and in non-closed environment nucleic or bioxin to external diffusion.
The course of work of the present invention is: at first will be transported to setting-out vaporising device 1 through the solid waste of pulverizing and carry out drying or liquid radioactive waste is transported to setting-out evaporation/carbonizing plant 2, setting-out vaporising device 1 upper end layout has contactless material infrared temperature measurement apparatus 13, board plug type gate 14, macroscopic view to detect camera head 12 and the measurement result that provides according to infrared temperature measurement apparatus 13 is carried out the microwave heating unit 11 that usefulness microwave array antenna technology that feed-in dispatches is determined the polynary combination of magnetic-control array by computer control.Setting-out evaporation/carbonizing plant 2 upper end layouts have contactless material temperature measuring equipment 23, reinforced apparatus for measuring charge level 24, macroscopic view to detect the microwave heating unit 21 that usefulness microwave array antenna technology that measurement result that camera head 22, contact material temperature measuring equipment 25 and contact material temperature measuring equipment 25 provide carries out the feed-in scheduling by computer control is determined the polynary combination of magnetic-control array.This cover combined system can realize setting-out evaporation and temperature control automatically according to setup parameter and temperature measuring equipment 25 feedback result closed-loop controls.Dried solid waste further subtracts appearance carbonization in setting-out evaporation/carbonizing plant 2 to be realized.Gas that solid waste pulverizing, liquid radioactive waste or solid waste drying and solid waste carbonization produce and hot steam directly enter cold-trap 3 under the effect of pressure reduction be trapped gasoloid by chilling, and the formation condition of bioxin is destroyed simultaneously.System's pressure reduction is mainly provided by vacuum system 7.In the vacuum system of connection 1,2,3, efficient nuclear level filtrator 4, condenser 5 and active carbon filter 6 are set to guarantee the qualified discharge of tail gas.For the raffinate that produces in cold-trap 3 and the condenser 5, can be used as liquid waste and be advanced into again and handle the back qualified discharge in the device 2.Function switching in the technological process is finished under the control of computing machine automatically by electrically operated valve 8.
Radioactive waste subtracts appearance process nucleic with the technological process of bioxin control is transported to setting-out evaporation/carbonizing plant 2, cold-trap 3, an efficient nuclear grade filtrator 4, condenser 5, active carbon filter 6, vacuum system 7 by solid waste setting-out vaporising device 1, liquid radioactive waste forms.
Claims (8)
1. disposal system that contains radioactive waste, it is characterized in that: the described disposal system that contains radioactive waste comprises capacity-reduction device and the exhaust gas processing device that links to each other with the capacity-reduction device pipeline; Described capacity-reduction device and exhaust gas processing device are co-located in the vacuum environment.
2. the disposal system that contains radioactive waste according to claim 1, it is characterized in that: described exhaust gas processing device comprises cold-trap and the filtration unit that links to each other with the cold-trap pipeline, and described capacity-reduction device, cold-trap and filtration unit link to each other by pipeline successively.
3. the disposal system that contains radioactive waste according to claim 2 is characterized in that: described filtration unit comprises first filtrator, condenser and second filtrator; Described cold-trap inserts first filtrator; Described first filtrator inserts second filtrator by condenser; Described condenser inserts cold-trap; Described second filtrator is an active carbon filter.
4. according to claim 2 or the 3 described disposal systems that contain radioactive waste, it is characterized in that: described capacity-reduction device comprises setting-out evaporation or carbonizing plant and coupled sample input end; Described sample input end inserts cold-trap by setting-out evaporation or carbonizing plant.
5. the disposal system that contains radioactive waste according to claim 4 is characterized in that: described setting-out evaporation or carbonizing plant comprise storage barrel, are arranged at the microwave heating unit and the temperature measuring equipment of storage barrel outside.
6. the disposal system that contains radioactive waste according to claim 5 is characterized in that: described temperature measuring equipment is infrared temperature-test sensor, contactless material temperature probe or contact material temperature probe.
7. the disposal system that contains radioactive waste according to claim 4 is characterized in that: described sample input end is solid-state castoff input end or liquid waste input end.
8. the disposal system that contains radioactive waste according to claim 1 is characterized in that: described disposal system is the disposal system that packaged type contains radioactive waste.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201110078397 CN102201271B (en) | 2011-03-30 | 2011-03-30 | System for processing radioactive wastes |
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|---|---|---|---|
| CN 201110078397 CN102201271B (en) | 2011-03-30 | 2011-03-30 | System for processing radioactive wastes |
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| CN102201271A true CN102201271A (en) | 2011-09-28 |
| CN102201271B CN102201271B (en) | 2013-10-30 |
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103714875A (en) * | 2013-12-30 | 2014-04-09 | 中国原子能科学研究院 | Device for removing Ag gel in nuclear waste water |
| CN103946924A (en) * | 2011-11-18 | 2014-07-23 | 太平洋水泥株式会社 | Method for removal of radioactive cesium and facility therefor |
| CN105448372A (en) * | 2014-08-12 | 2016-03-30 | 中核核电运行管理有限公司 | Method for cleaning and releasing control of discarded air cleaner metal frameworks in nuclear power plant |
| WO2017202178A1 (en) * | 2016-05-23 | 2017-11-30 | 中国工程物理研究院材料研究所 | Liquid-phase oxidative decomposition method for radioactively contaminated carbon-containing material |
| CN109994241A (en) * | 2017-12-31 | 2019-07-09 | 中国人民解放军63653部队 | Hundred feather weight solid radioactive waste curing process systems |
| CN111849529A (en) * | 2020-07-20 | 2020-10-30 | 中国工程物理研究院材料研究所 | Thermal cracking treatment device and method for radioactive waste resin |
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Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103946924A (en) * | 2011-11-18 | 2014-07-23 | 太平洋水泥株式会社 | Method for removal of radioactive cesium and facility therefor |
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| CN103714875A (en) * | 2013-12-30 | 2014-04-09 | 中国原子能科学研究院 | Device for removing Ag gel in nuclear waste water |
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| CN105448372A (en) * | 2014-08-12 | 2016-03-30 | 中核核电运行管理有限公司 | Method for cleaning and releasing control of discarded air cleaner metal frameworks in nuclear power plant |
| WO2017202178A1 (en) * | 2016-05-23 | 2017-11-30 | 中国工程物理研究院材料研究所 | Liquid-phase oxidative decomposition method for radioactively contaminated carbon-containing material |
| CN109994241A (en) * | 2017-12-31 | 2019-07-09 | 中国人民解放军63653部队 | Hundred feather weight solid radioactive waste curing process systems |
| CN111849529A (en) * | 2020-07-20 | 2020-10-30 | 中国工程物理研究院材料研究所 | Thermal cracking treatment device and method for radioactive waste resin |
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| CN102201271B (en) | 2013-10-30 |
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Denomination of invention: Treatment system containing radioactive waste Effective date of registration: 20230328 Granted publication date: 20131030 Pledgee: Bank of China Limited Xiamen hi tech Park sub branch Pledgor: HUANCHUANG (XIAMEN) TECHNOLOGY Co.,Ltd. Registration number: Y2023980036583 |