CN104966540A - Plasma low-intermediate level radioactive solid waste disposal method - Google Patents
Plasma low-intermediate level radioactive solid waste disposal method Download PDFInfo
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- CN104966540A CN104966540A CN201510237616.5A CN201510237616A CN104966540A CN 104966540 A CN104966540 A CN 104966540A CN 201510237616 A CN201510237616 A CN 201510237616A CN 104966540 A CN104966540 A CN 104966540A
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- 238000000034 method Methods 0.000 title claims abstract description 58
- 230000002285 radioactive effect Effects 0.000 title claims abstract description 23
- 239000002910 solid waste Substances 0.000 title claims abstract description 20
- 239000002699 waste material Substances 0.000 claims abstract description 24
- 239000011521 glass Substances 0.000 claims abstract description 22
- 238000002844 melting Methods 0.000 claims abstract description 17
- 230000008018 melting Effects 0.000 claims abstract description 17
- 238000009413 insulation Methods 0.000 claims abstract description 12
- 238000000137 annealing Methods 0.000 claims abstract description 11
- 238000001514 detection method Methods 0.000 claims abstract description 8
- 238000012545 processing Methods 0.000 claims abstract description 6
- 238000009270 solid waste treatment Methods 0.000 claims description 19
- 239000002901 radioactive waste Substances 0.000 claims description 11
- 239000002184 metal Substances 0.000 claims description 10
- 239000002671 adjuvant Substances 0.000 claims description 9
- 239000000463 material Substances 0.000 claims description 9
- 239000005337 ground glass Substances 0.000 claims description 8
- 238000010583 slow cooling Methods 0.000 claims description 7
- 241001300078 Vitrea Species 0.000 claims description 6
- 230000015572 biosynthetic process Effects 0.000 claims description 6
- 238000005259 measurement Methods 0.000 claims description 6
- 238000012360 testing method Methods 0.000 claims description 6
- 239000011347 resin Substances 0.000 claims description 5
- 229920005989 resin Polymers 0.000 claims description 5
- 238000013467 fragmentation Methods 0.000 claims description 4
- 238000006062 fragmentation reaction Methods 0.000 claims description 4
- 239000012774 insulation material Substances 0.000 claims description 4
- 239000011490 mineral wool Substances 0.000 claims description 4
- 238000009832 plasma treatment Methods 0.000 claims description 4
- 239000004033 plastic Substances 0.000 claims description 4
- 229920003023 plastic Polymers 0.000 claims description 4
- -1 clothing Substances 0.000 claims description 3
- 239000012141 concentrate Substances 0.000 claims description 3
- 239000006185 dispersion Substances 0.000 claims description 3
- 230000008676 import Effects 0.000 claims description 3
- 238000003032 molecular docking Methods 0.000 claims description 3
- 238000005192 partition Methods 0.000 claims description 3
- 238000005303 weighing Methods 0.000 claims description 3
- 238000001816 cooling Methods 0.000 abstract description 2
- 241001062472 Stokellia anisodon Species 0.000 abstract 2
- 239000000654 additive Substances 0.000 abstract 1
- 238000007599 discharging Methods 0.000 abstract 1
- 238000007711 solidification Methods 0.000 description 5
- 230000008023 solidification Effects 0.000 description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 4
- 238000005516 engineering process Methods 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- 230000004308 accommodation Effects 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 239000003513 alkali Substances 0.000 description 1
- 239000004568 cement Substances 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 238000000354 decomposition reaction Methods 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 238000010304 firing Methods 0.000 description 1
- 150000002240 furans Chemical class 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000010805 inorganic waste Substances 0.000 description 1
- 239000002925 low-level radioactive waste Substances 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 231100000252 nontoxic Toxicity 0.000 description 1
- 230000003000 nontoxic effect Effects 0.000 description 1
- 150000002894 organic compounds Chemical class 0.000 description 1
- 238000006722 reduction reaction Methods 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 150000003384 small molecules Chemical class 0.000 description 1
- 239000002900 solid radioactive waste Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 231100000331 toxic Toxicity 0.000 description 1
- 230000002588 toxic effect Effects 0.000 description 1
Classifications
-
- 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
- G21F9/301—Processing by fixation in stable solid media
- G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
- G21F9/305—Glass or glass like matrix
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- Chemical & Material Sciences (AREA)
- Inorganic Chemistry (AREA)
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Processing Of Solid Wastes (AREA)
- Gasification And Melting Of Waste (AREA)
Abstract
The invention discloses a plasma low-intermediate level radioactive solid waste disposal method, comprising: classifying radioactive solid wastes, placing the solid wastes in different classifications in different waste bins according to classification, and metering the wastes; adding corresponding formula additives to the metered wastes in sequence according to classification, and performing whole bin breaking processing, transporting to a plasma smelt furnace for melting treatment; melt discharged from the smelt furnace discharging to a reception container, after the reception container is full, the container being transferred to a heat insulation annealing station for heat insulation, annealing, and slowly cooling, to form uniform texture glass HLW; transferring the reception container which is solidified to a dosage detection station, and performing radioactive dosage detection and transferring and storing the reception container. Using the method can form uniform texture glass HLW in good performance and improve processing efficiency.
Description
Technical field
The present invention relates to the waste processing arts of nuclear power plant, particularly a kind of plasma low in put solid waste treatment method.
Background technology
Nuclear power plant inevitably produces a certain amount of radioactive waste in operation and maintenance process, and these radioactive wastes can final disposal after must pass through the stable containing process of such as radioactive nuclide.At present, for solid radioactive waste, the general treatment process of domestic nuclear power plant is cement solidification technology, but its compatibilization is excessive, brings very large pressure to radioactive-waste disposal.
In addition, have also appeared a kind of plasma technique in the prior art to process radioactive waste.This plasma technique is the feature utilizing hot plasma to have higher temperature and energy density, fast refuse is carried out Pintsch process, its product is glassy state inorganics, the gas produced is by the reduction reaction under hot environment, be decomposed into atom and the simplest molecule, some toxic organic compounds (particularly bioxin and furans) in radioactive waste thoroughly can be decomposed into nontoxic small-molecule substance.
Therefore plasma treatment technique is applicable to low level waste disposal in nuclear power station great majority, be particularly useful for the process of incombustible refuse.For debirs, the high temperature of hot plasma can make organic principle decompose, and the micro-molecular gas after decomposition burns further under the environment of aerobic; For inorganic wastes, the high temperature of hot plasma also can make inorganic constituents melting, thus contains radioactive nuclide, forms glass solidified body after cooling.
But the quality of input and output material process directly affects the performance of firming body.Solid waste treatment method is put in how low by plasma, to ensure that glass solidified body is formed, and glass solidified body has the features such as certain mechanical property, stability, radioresistance and water resisting property, and avoids operating personnel to be subject to the impact of irradiation dose, a kind of beyond doubt challenge.
Summary of the invention
Technical matters to be solved by this invention is, provide a kind of low for plasma in put solid waste treatment method, can be formed homogeneous and performance good glass solidified body, and can treatment effeciency be improved.
For solving the problems of the technologies described above, the embodiment of the present invention puts solid waste treatment method in providing a kind of plasma low, comprising:
Radioactive solid waste is classified, and carries out process of sorting or break, and different classes of solid waste category is contained in different pails for used dressings respectively, and measure;
Successively the refuse category after above-mentioned metering is added the adjuvant of corresponding formula, and carry out whole bucket break process, by spiral conveyer, the refuse material after fragmentation is flowed to plasma melting stove at the uniform velocity, equably and carry out melt process;
Receiving vessel opening and melting furnace discharge system are exported and connects, Vitrea formation temperature under starting protection system makes temperature rise to this formula, open discharge system, the fused mass that melting furnace is discharged drains in receiving vessel, after receiving vessel is filled, be transferred to that insulation annealing station carries out being incubated, anneals, Slow cooling, form homogeneous ground glass solidified body;
Receiving vessel after having solidified is transported to dose measurement station, carries out radioactive dosage detection and transhipment storage.
Preferably, described radioactive solid waste to be classified, and the step of process of carrying out sorting or break comprises:
According to subtracting appearance degree after plasma treatment, radioactive waste being classified, being divided into easily subtracting to hold refuse and not easily subtract and holding the large class of refuse two, and processing respectively;
Wherein, to not easily subtracting the metal put in injectivity waste, the direct barrelling of mud class is fixing processes and store, and commute subtracts the rock wool class insulation material put in injectivity waste and uses as adjuvant.
Preferably, described radioactive solid waste to be classified, and the step of process of carrying out sorting or break comprises:
Commute subtracts the paper put in injectivity waste, clothing, plastics, rubber-like waste delivery on travelling belt, imports sorting system into, is sorted out by metal in sorting system, then by other refuse barrelling; If the place dispersion dosage barrelling having high dose to concentrate, is transported to metrology station and carries out Weighing after installing, and stores relevant information.
Preferably, described radioactive solid waste to be classified, and the step of process of carrying out sorting or break comprises;
For easily subtract put spent resin in injectivity waste be divided into two classes according to Acidity of Aikalinity, barrelling metering respectively, is then separated storage.
Preferably, described radioactive solid waste to be classified, and the step of process of carrying out sorting or break comprises;
Be transported to tear open and cut hot cell by easily subtracting the filter cartridge put in injectivity waste and carry out partition process, metalwork is torn open, cut out, the part of wherein recoverable is reclaimed, wherein expendable part is then transported and fix process storage;
Miscellaneous part except metal is measured, and loads in pail for used dressings and store, recording-related information.
Preferably; described receiving vessel opening and melting furnace discharge system outlets connects; Vitrea formation temperature under starting protection system makes temperature rise to this formula, open discharge system, the step that the fused mass that melting furnace is discharged drains in receiving vessel specifically comprises:
Open glass solidified body protection system shield door, the receiving vessel of sky is proceeded to protection system to splicing station, receiving vessel enters rear and closes shield door;
Receiving vessel opening exports with discharge system and docks by startup lifting body;
Starting protection system, opens discharge system after protection system is stable and carries out discharge process.
Preferably, described receiving vessel after having solidified is transported to dose measurement station, carries out radioactive dosage detection and the step that transhipment stores comprises further:
The standard compliant glass solidified body cross-docking of testing result is stored, to testing result non-compliant glass solidified body suit cask flask, then carries out transhipment and store.
Implement the present invention, there is following beneficial effect:
Solid waste treatment method is put during a kind of plasma provided in the embodiment of the present invention is low, classification process can be carried out to solid waste, be applicable to the process of many kinds of solids radioactive waste input and output material, and after carrying out classification process, corresponding different vitrifacation formulas, meanwhile, be conducive to the interpolation quantizing adjuvant after carrying out classification metering, glass solidification weight can be ensured;
Meanwhile, whole technological process all adopts pipelining to operate, and is conducive to improving treatment effeciency, and can reduce the radiation to operating personnel;
And; due in vitreum solidification process; have employed protection system; and receiving vessel needs after filling to be transferred to, and insulation annealing station carries out being incubated, anneals, Slow cooling; can ensure to form homogeneous ground glass solidified body; make obtained glass solidified body stable performance, there is the features such as certain mechanical property, stability, radioresistance and water resisting property.
Accompanying drawing explanation
In order to be illustrated more clearly in the embodiment of the present invention or technical scheme of the prior art, be briefly described to the accompanying drawing used required in embodiment or description of the prior art below, apparently, accompanying drawing in the following describes is only some embodiments of the present invention, for those of ordinary skill in the art, under the prerequisite not paying creative work, other accompanying drawing can also be obtained according to these accompanying drawings.
Fig. 1 be a kind of plasma provided by the invention low in put main flow schematic diagram in an embodiment of solid waste treatment method;
Fig. 2 is the more detailed schematic flow sheet corresponding to Fig. 1;
Fig. 3 be a kind of plasma provided by the invention low in put in another embodiment of solid waste treatment method local flow process signal.
Embodiment
Below in conjunction with the accompanying drawing in the embodiment of the present invention, be clearly and completely described the technical scheme in the embodiment of the present invention, obviously, described embodiment is only the present invention's part embodiment, instead of whole embodiments.Based on the embodiment in the present invention, those of ordinary skill in the art, not making the every other embodiment obtained under creative work prerequisite, belong to the scope of protection of the invention.
As shown in Figure 1, show the low main flow schematic diagram putting an embodiment of solid waste treatment method in plasma provided by the invention, in this embodiment, mainly for ensureing that radioactive waste input and output material rationally and ensure that glass solidified body is formed, meet glass solidified body performance requirement, homogeneous ground glass solidified body can be formed after this input and output material process, there is the features such as certain mechanical property, stability, radioresistance and water resisting property.Particularly, put solid waste treatment method during this plasma is low, comprise the steps:
Step S10, classifies to radioactive solid waste, and carries out process of sorting or break, and is contained in respectively in different pails for used dressings by different classes of solid waste category, and measures;
Step S12, adds the adjuvant of corresponding formula successively, and carries out whole bucket break process, by spiral conveyer, the refuse material after fragmentation is flowed to plasma melting stove at the uniform velocity, equably and carry out melt process by the refuse category after above-mentioned metering;
Step S14, receiving vessel opening and melting furnace discharge system are exported and connects, Vitrea formation temperature under starting protection system makes temperature rise to this formula, open discharge system, the fused mass that melting furnace is discharged drains in receiving vessel, after receiving vessel is filled, be transferred to that insulation annealing station carries out being incubated, anneals, Slow cooling, form homogeneous ground glass solidified body;
Step S16, is transported to dose measurement station by the receiving vessel after having solidified, and carries out radioactive dosage detection and transhipment storage.
As shown in Figure 2, be the more detailed schematic flow sheet corresponding to Fig. 1; It specifically comprises the steps:
In step slo, according to subtracting appearance degree after plasma treatment, radioactive waste being classified, being divided into easily subtracting to hold refuse and not easily subtract and holding the large class of refuse two, and processing respectively;
Wherein, not easily subtract and put injectivity waste according to being divided into the insulation material classes such as metal, mud class and rock wool by disposal and utilization.To not easily subtracting the metal put in injectivity waste, mud class, owing to utilizing, then directly barrelling is fixing processes and stores, and commute subtracts the rock wool class insulation material put in injectivity waste and uses as adjuvant.
Easily subtract and put injectivity waste and according to type classify, be divided into class, spent resin class and the filtration core subclasses such as paper, clothing, plastics, rubber.Commute subtracts the paper put in injectivity waste, clothing, plastics, rubber-like waste delivery on travelling belt, imports sorting system into, is sorted out by metal in sorting system, then by other refuse barrelling; If the place dispersion dosage barrelling having high dose to concentrate, is transported to metrology station and carries out Weighing after installing, and stores relevant information;
Put spent resin in injectivity waste do not need to enter sorting system for easily subtracting, only need according to source refuse acid, alkali resin two class, barrelling metering respectively, is then separated storage;
Be transported to tear open and cut hot cell by easily subtracting the filter cartridge put in injectivity waste and carry out partition process, metalwork is torn open, cut out, the part of wherein recoverable is reclaimed, wherein expendable part is then transported and fix process storage; Miscellaneous part except metal is measured, and loads in pail for used dressings and store, recording-related information.
In step s 12, successively the refuse category after above-mentioned metering is added the adjuvant of corresponding formula, the number added determines according to the amount of refuse, and carry out whole bucket break process, by spiral conveyer, the refuse material after fragmentation is flowed to plasma melting stove at the uniform velocity, equably and carry out melt process, wherein it should be noted that and need to process the another kind of refuse of reprocessing after a class refuse;
In step S14, pass through discharge system, the fused mass that melting furnace is discharged drains in receiving vessel, after receiving vessel is filled, be transferred to that insulation annealing station carries out being incubated, anneals, Slow cooling, form homogeneous ground glass solidified body, wherein, corresponding to different formulas, the scheme of corresponding different insulation annealings;
In step s 16, receiving vessel after having solidified is transported to dose measurement station, carry out radioactive dosage detection and transhipment storage, particularly, the standard compliant glass solidified body cross-docking of testing result is stored, to testing result non-compliant glass solidified body suit cask flask, then carry out transhipment and store.
As shown in Figure 3, be a kind of plasma provided by the invention low in put in another embodiment of solid waste treatment method local flow process signal.The difference of itself and Fig. 2 is, has been further listed in the step of more details when discharge system carries out work in figure 3.Particularly, step S14 comprises following step further:
Open glass solidified body protection system shield door, wherein glass solidified body protection system is a spatial accommodation with function of shielding, and the inside is provided with firing equipment, can realize multiple heating and thermal insulation scheme;
The receiving vessel of sky is proceeded to protection system to splicing station;
Receiving vessel enters rear and closes shield door;
Receiving vessel opening exports with discharge system and docks by startup lifting body;
Starting protection system, after protection system is stable (temperature being risen to the Vitrea formation temperature under this formula), opens discharge system and carries out discharge process;
After receiving vessel is filled, be transferred to that insulation annealing station carries out being incubated, anneals, Slow cooling, form homogeneous ground glass solidified body, wherein, corresponding to different formulas, the scheme of corresponding different insulation annealings.
Other steps in the present embodiment, with reference to the aforementioned description to Fig. 2, can not describe in detail a bit.
Implement the present invention, there is following beneficial effect:
Solid waste treatment method is put during a kind of plasma provided in the embodiment of the present invention is low, classification process can be carried out to solid waste, be applicable to the process of many kinds of solids radioactive waste input and output material, and after carrying out classification process, corresponding different vitrifacation formulas, meanwhile, be conducive to the interpolation quantizing adjuvant after carrying out classification metering, glass solidification weight can be ensured;
Meanwhile, whole technological process all adopts pipelining to operate, and is conducive to improving treatment effeciency, and can reduce the radiation to operating personnel;
And; due in vitreum solidification process; have employed protection system; and receiving vessel needs after filling to be transferred to, and insulation annealing station carries out being incubated, anneals, Slow cooling; can ensure to form homogeneous ground glass solidified body; make obtained glass solidified body stable performance, there is the features such as certain mechanical property, stability, radioresistance and water resisting property.
Above disclosedly be only a kind of preferred embodiment of the present invention, certainly can not limit the interest field of the present invention with this, therefore according to the equivalent variations that the claims in the present invention are done, still belong to the scope that the present invention is contained.
Claims (7)
1. plasma low in put a solid waste treatment method, it is characterized in that, comprising:
Radioactive solid waste is classified, and carries out process of sorting or break, and different classes of solid waste category is contained in different pails for used dressings respectively, and measure;
Successively the refuse category after above-mentioned metering is added the adjuvant of corresponding formula, and carry out whole bucket break process, by spiral conveyer, the refuse material after fragmentation is flowed to plasma melting stove at the uniform velocity, equably and carry out melt process;
Receiving vessel opening and melting furnace discharge system are exported and connects, Vitrea formation temperature under starting protection system makes temperature rise to this formula, open discharge system, the fused mass that melting furnace is discharged drains in receiving vessel, after receiving vessel is filled, be transferred to that insulation annealing station carries out being incubated, anneals, Slow cooling, form homogeneous ground glass solidified body;
Receiving vessel after having solidified is transported to dose measurement station, carries out radioactive dosage detection and transhipment storage.
2. a kind of plasma as claimed in claim 1 low in put solid waste treatment method, it is characterized in that, described radioactive solid waste to be classified, and the step of process of carrying out sorting or break comprises:
According to subtracting appearance degree after plasma treatment, radioactive waste being classified, being divided into easily subtracting to hold refuse and not easily subtract and holding the large class of refuse two, and processing respectively;
Wherein, to not easily subtracting the metal put in injectivity waste, the direct barrelling of mud class is fixing processes and store, and commute subtracts the rock wool class insulation material put in injectivity waste and uses as adjuvant.
3. a kind of plasma as claimed in claim 2 low in put solid waste treatment method, it is characterized in that, described radioactive solid waste to be classified, and the step of process of carrying out sorting or break comprises:
Commute subtracts the paper put in injectivity waste, clothing, plastics, rubber-like waste delivery on travelling belt, imports sorting system into, is sorted out by metal in sorting system, then by other refuse barrelling; If the place dispersion dosage barrelling having high dose to concentrate, is transported to metrology station and carries out Weighing after installing, and stores relevant information.
4. a kind of plasma as claimed in claim 2 low in put solid waste treatment method, it is characterized in that, described radioactive solid waste to be classified, and the step of process of carrying out sorting or break comprises;
For easily subtract put spent resin in injectivity waste be divided into two classes according to Acidity of Aikalinity, barrelling metering respectively, is then separated storage.
5. a kind of plasma as claimed in claim 2 low in put solid waste treatment method, it is characterized in that, described radioactive solid waste to be classified, and the step of process of carrying out sorting or break comprises;
Be transported to tear open and cut hot cell by easily subtracting the filter cartridge put in injectivity waste and carry out partition process, metalwork is torn open, cut out, the part of wherein recoverable is reclaimed, wherein expendable part is then transported and fix process storage;
Miscellaneous part except metal is measured, and loads in pail for used dressings and store, recording-related information.
6. during a kind of plasma as described in any one of claim 2 to 5 is low, put solid waste treatment method; it is characterized in that; described receiving vessel opening and melting furnace discharge system outlets connects; Vitrea formation temperature under starting protection system makes temperature rise to this formula; open discharge system, the step that the fused mass that melting furnace is discharged drains in receiving vessel specifically comprises:
Open glass solidified body protection system shield door, the receiving vessel of sky is proceeded to protection system to splicing station, receiving vessel enters rear and closes shield door;
Receiving vessel opening exports with discharge system and docks by startup lifting body;
Starting protection system, opens discharge system after protection system is stable and carries out discharge process.
7. a kind of plasma as claimed in claim 6 low in put solid waste treatment method, it is characterized in that, described receiving vessel after having solidified is transported to dose measurement station, carry out radioactive dosage detection and the step that transhipment stores comprises further:
The standard compliant glass solidified body cross-docking of testing result is stored, to testing result non-compliant glass solidified body suit cask flask, then carries out transhipment and store.
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Cited By (8)
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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 |
| CN106910545A (en) * | 2017-03-23 | 2017-06-30 | 中国原子能科学研究院 | A kind of startup method for the treatment of radioactive liquid waste cold crucible glass solidification |
| CN107274952A (en) * | 2017-07-13 | 2017-10-20 | 碧海舟（北京）节能环保装备有限公司 | The processing system of middle low-activity nuke rubbish and the electricity generation system with it |
| CN108831578A (en) * | 2017-09-30 | 2018-11-16 | 四川宇称科技有限公司 | A method of realizing the automatic pre-sorting of radioactive waste |
| CN110176322A (en) * | 2019-05-13 | 2019-08-27 | 江苏天楹环保能源成套设备有限公司 | A kind of middle low-activity solid waste volume reduction processing system and its method |
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| CN114068057A (en) * | 2021-11-11 | 2022-02-18 | 中广核研究院有限公司 | Glass solidification treatment method for radioactive waste |
| CN114315134A (en) * | 2021-12-31 | 2022-04-12 | 西南科技大学 | Method for treating high-level radioactive waste by direct vitrification of discharge plasma |
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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 |
| CN106910545A (en) * | 2017-03-23 | 2017-06-30 | 中国原子能科学研究院 | A kind of startup method for the treatment of radioactive liquid waste cold crucible glass solidification |
| CN106910545B (en) * | 2017-03-23 | 2018-08-24 | 中国原子能科学研究院 | A kind of startup method for the processing of radioactive liquid waste cold crucible glass solidification |
| CN107274952A (en) * | 2017-07-13 | 2017-10-20 | 碧海舟（北京）节能环保装备有限公司 | The processing system of middle low-activity nuke rubbish and the electricity generation system with it |
| CN107274952B (en) * | 2017-07-13 | 2023-08-29 | 北京碧海能源装备有限公司 | Treatment system of medium-low radioactivity nuclear waste and power generation system with same |
| CN108831578A (en) * | 2017-09-30 | 2018-11-16 | 四川宇称科技有限公司 | A method of realizing the automatic pre-sorting of radioactive waste |
| CN110176322A (en) * | 2019-05-13 | 2019-08-27 | 江苏天楹环保能源成套设备有限公司 | A kind of middle low-activity solid waste volume reduction processing system and its method |
| CN111633001A (en) * | 2020-06-08 | 2020-09-08 | 盛亚林 | Industrial waste residue processing apparatus |
| CN111633001B (en) * | 2020-06-08 | 2022-07-01 | 青岛达能环保设备股份有限公司 | Industrial waste residue processing apparatus |
| CN114068057A (en) * | 2021-11-11 | 2022-02-18 | 中广核研究院有限公司 | Glass solidification treatment method for radioactive waste |
| CN114068057B (en) * | 2021-11-11 | 2024-03-19 | 中广核研究院有限公司 | Glass solidification treatment method for radioactive waste |
| CN114315134A (en) * | 2021-12-31 | 2022-04-12 | 西南科技大学 | Method for treating high-level radioactive waste by direct vitrification of discharge plasma |
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