CN110517803A - The processing method of radioactivity concentrate - Google Patents
The processing method of radioactivity concentrate Download PDFInfo
- Publication number
- CN110517803A CN110517803A CN201910717267.5A CN201910717267A CN110517803A CN 110517803 A CN110517803 A CN 110517803A CN 201910717267 A CN201910717267 A CN 201910717267A CN 110517803 A CN110517803 A CN 110517803A
- Authority
- CN
- China
- Prior art keywords
- pail pack
- radioactivity concentrate
- processing method
- radioactivity
- concentrate
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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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
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/08—Processing by evaporation; by distillation
-
- 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
- G21F9/04—Treating liquids
- G21F9/20—Disposal of liquid waste
- G21F9/22—Disposal of liquid waste by storage in a tank or other container
-
- 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
- G21F9/36—Disposal of solid waste by packaging; by baling
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Environmental & Geological Engineering (AREA)
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Abstract
The invention discloses a kind of processing methods of radioactivity concentrate, comprising the following steps: radioactivity concentrate is transported in pail pack;Pail pack is heated, the radioactivity concentrate evaporation in pail pack obtains solid radiation material (such as salt-cake);The pail pack that solid radiation material (such as salt-cake) will be filled is encased in high integrality container.Processing method in the present invention makes the volume reduction ratio of radioactivity concentrate reach 6~8, 10 times or more are improved compared to traditional cement curing process (capacity increasing process), the present invention is using pail pack as the container of evaporation, solid radiation material can be formed directly in pail pack, it is packed into high integrality container together with pail pack, leakage problem of the solid radiation material in cargo handling process is avoided (as generated radioactive dust, aerosol etc.), convenient for the transport and disposition of subsequent solid radiation material, the waste for improving nuclear power plant minimizes level, reduce influence of the radioactive solid waste to environment.
Description
Technical field
The invention belongs to Radwastes treatment technical fields, and in particular to a kind of processing method of radioactivity concentrate.
Background technique
In PWR nuclear power plant, when radioactive liquid waste activity concentration be more than emission limit, filtered can not still discharge or
Chemical impurity content is high, and when can not handle using desalination device, concentration, the condensation that evaporator generates can be evaporated using evaporator
Liquid monitoring discharge, evaporation concentrated solution contain higher salinity and most of radionuclide, are solidified or used
Other modes processing.Currently, domestic in-service nuclear power plant uses the concentration of low, the middle radioactive level of cement solidification process
Liquid, waste increase-volume is larger, and the temporary and final disposal to waste packet in nuclear power plant all causes certain pressure.
Summary of the invention
The technical problem to be solved by the present invention is to aiming at the above shortcomings existing in the prior art, provide a kind of radioactivity
The processing method of concentrate, radioactivity concentrate evaporative crystallization in pail pack form solid salt block, solid radiation material (ratio
Such as salt-cake) it is packed into together with pail pack in high integrality container, it effectively prevents solid radiation material (such as salt-cake) and is filling
Leakage problem during unloading can be improved the waste of nuclear power plant convenient for the transport and disposition of subsequent solid radiation material
It minimizes horizontal.
The processing method that technical solution used by present invention problem is to provide a kind of radioactivity concentrate is solved, packet
Include following steps:
Radioactivity concentrate is transported in pail pack;
Pail pack is heated, the radioactivity concentrate evaporation in pail pack obtains solid radiation material;
The pail pack of solid radiation material will be filled, is encased in high integrality container.
Preferably, solid radiation material is crystal salt.
Preferably, when the step heats pail pack, the pressure in pail pack is tiny structure.
Preferably, the step will fill the pail pack of solid radiation material, before being encased in high integrality container
It further comprises the steps of: and the solid radiation material in pail pack is dried.
Preferably, the processing method of the radioactivity concentrate, it is further comprising the steps of: by purification device to adding
The exhaust of the pail pack of heat carries out gas-liquid separation, and the liquid that gas-liquid separation goes out is flow back into pail pack, the gas that gas-liquid separation is gone out
Body is passed through condensing unit and is condensed, to condensation and separation of liquid be collected, by condensing unit condensation and separation of not coagulating
Gas.
Preferably, the condition of the heating stepses are as follows: heating temperature is 50~300 DEG C.
Preferably, the step heats pail pack specifically: one or several regions of pail pack are heated,
Heating region is part pail pack.
Preferably, radioactivity concentrate is transported in pail pack by the step specifically: will be put by metering device
Penetrating property concentrate is delivered continuously in pail pack, alternatively, by metering device every time in preset volume transportation to pail pack.
Preferably, the step heats pail pack specifically: by electric heater unit, hot-air, hot oil
Any one heated.
Preferably, the condition of heating end is carried out to pail pack are as follows: liquid level, solid radiation material in pail pack contain
Water rate, temperature, delivery temperature, one or several in exhaust steam moisture reach preset requirement condition.
Preferably, the material of pail pack is thermally conductive metal.
The processing method of radioactivity concentrate in the present invention is so that the volume reduction ratio of radioactivity concentrate reaches 6~8
10 times of raising or more of traditional cement curing process (capacity increasing process), the present invention are evaporated using pail pack as radioactivity concentrate
Container, solid radiation material (such as salt-cake) can directly be used as packing container pail pack in be formed, radioactive solid
Body material (such as salt-cake) is packed into high integrality container together with pail pack, is effectively prevented solid radiation material and is being loaded and unloaded
Leakage problem in the process can be improved the waste of nuclear power plant most convenient for the transport and disposition of subsequent solid radiation material
Smallization is horizontal, reduces influence of the radioactive solid waste to environment.
Detailed description of the invention
Fig. 1 is the structural schematic diagram of the processing system of the radioactivity concentrate in the embodiment of the present invention 2.
In figure: 1- surge tank;2- metering device;3- valve;4- pail pack;5- barrels of ontologies;6- seals bung;7- heating dress
It sets;8- purification device;9- condensing unit;The first valve of 10-;11- condensate liquid receiving slit;The second valve of 12-;13- third valve;
14- blower;15- regulating valve;The 4th valve of 16-.
Specific embodiment
Technical solution in order to enable those skilled in the art to better understand the present invention, with reference to the accompanying drawing and specific embodiment party
Present invention is further described in detail for formula.
The embodiment of this patent is described below in detail, examples of the embodiments are shown in the accompanying drawings, wherein from beginning to end
Same or similar label indicates same or similar element or element with the same or similar functions.Below with reference to attached
The embodiment of figure description is exemplary, and is only used for explaining this patent, and cannot be understood as a limitation of this patent.
Embodiment 1
The present embodiment provides a kind of processing methods of radioactivity concentrate, comprising the following steps:
Radioactivity concentrate is transported in pail pack;
Pail pack is heated, the radioactivity concentrate evaporation in pail pack obtains solid radiation material;
The pail pack of solid radiation material will be filled, is encased in high integrality container.
The processing method of radioactivity concentrate in the present embodiment, so that the volume reduction ratio of radioactivity concentrate reaches 6~8,
It is 10 times of raising or more of traditional cement curing process (capacity increasing process), the present embodiment is using pail pack as radioactivity concentrate
The container of evaporation, solid radiation material can be formed directly in the pail pack for being used as packing container, solid radiation material
It is packed into together with pail pack in high integrality container, effectively prevents leakage of the solid radiation material in cargo handling process and ask
Topic, convenient for the transport and disposition of subsequent solid radiation material, the waste minimum that can be improved nuclear power plant is horizontal, and reduction is put
Influence of the penetrating property solid waste to environment.
Embodiment 2
As shown in Figure 1, the present embodiment provides a kind of processing systems of radioactivity concentrate, comprising:
Surge tank 1, for buffering radioactivity concentrate;
Metering device 2 is connect with surge tank 1, and metering device 2 is for measuring the radioactivity for flowing to pail pack 4 by surge tank 1
The flow of concentrate, specifically, metering device 2 includes two sequentially connected valves 3, the setting of two valves 3 surge tank 1 with
On pipeline between pail pack 4, two cooperations of valve 3 make radioactivity concentrate that pail pack 4 be added by several times, and each additional amount is
The volume of pipeline between two valves 3.
Pail pack 4 is connect with metering device 2, and pail pack 4 is used to hold the radioactivity concentrate of crystallization to be evaporated;Packaging
Bucket 4 includes bucket ontology 5 and sealing bung 6, and bucket ontology 5 is matched with sealing bung 6 by jacking apparatus and merges sealing.
Heating device 7, for being heated to pail pack 4;Heating device 7 is set to bucket wall and the bucket bottom of pail pack 4.
Purification device 8 is connect with pail pack 4, and purification device 8 is used for the exhaust to the pail pack 4 of heating and carries out gas-liquid point
From the liquid that gas-liquid separation goes out is flow back into pail pack 4, and the gas that gas-liquid separation goes out flows into condensing unit 9 and condensed;Purification
Device 8 can remove but be not limited to mist.Purification device 8 is using cleaning device again or to use disposable purification device.
Using cleaning device again, ejected wash water is recoiled to being evaporated in pail pack 4 when use, reduce secondary waste and generate
Amount.
Condensing unit 9 is connect with purification device 8, and condensing unit 9 is used to condense the gas that gas-liquid separation goes out;It is cold
Solidifying device 9 includes cooling water pipeline, and cooling water pipeline is provided with the second valve for providing cooling capacity on the entrance of cooling water pipeline
12, specifically, the condensing unit 9 in the present embodiment is vapour condensation device;
First valve 10 is set on the pipeline between purification device 8 and condensing unit 9;
Condensate liquid receiving slit 11 is connect with condensing unit 9, and condensate liquid receiving slit 11 is for receiving the condensation point of condensing unit 9
From the liquid to get off;
Third valve 13 is set on the pipeline between condensate liquid receiving slit 11 and condensing unit 9;
Blower 14 is connect with condensate liquid receiving slit 11, and the blower 14 and condensate liquid that blower 14 is used to connect it receive
Pipeline between slot 11 is aspirated;
Regulating valve 15 is set on the pipeline between blower 14 and condensate liquid receiving slit 11;
4th valve 16 is set on the outlet conduit of condensate liquid receiving slit 11, by 11 outlet conduit of condensate liquid receiving slit
Condensate liquid is discharged.
The present embodiment provides a kind of processing methods of radioactivity concentrate using above-mentioned processing unit, including following step
It is rapid:
(1) the radioactivity concentrate in surge tank 1 is delivered continuously in pail pack 4 by metering device 2, alternatively, logical
Metering device 2 is crossed every time in preset volume transportation to pail pack 4.Specifically, will be delayed in the present embodiment by metering device 2
The radioactivity concentrate rushed in tank 1 by the valve 3 of metering device 2 every time to be adjusted in preset volume transportation to pail pack 4
Flow.
(2) pail pack 4 is heated, heating temperature is 50~300 DEG C, under the conditions of tiny structure, putting in pail pack 4
Penetrating property concentrate temperature increases, and evaporative crystallization, and liquid phase thickens and forming salt, obtains solid radiation material, solid radiation
Material is crystal salt, and obtained solid radiation material is salt-cake (block).Specifically, the heating temperature in the present embodiment is 200
℃.Radioactive substance can be effectively prevented to Environment release in tiny structure condition.
Preferably, tiny structure can by blower 14, compressor or other air transporting arrangements in downstream suction come real
It is existing;Also the valve 3 with regulatory function can be set and cooperate blower 14, compressor or other air transporting arrangements to control packaging
Pressure in bucket 4.Specifically, tiny structure in the present embodiment is realized by blower 14 in downstream suction.
Preferably, pail pack 4 is heated specifically: by any in electric heater unit 7, hot-air, hot oil
It is a kind of to be heated.Specifically, being heated in the present embodiment by electric heater unit 7.Electric heater unit 7 is by giving different positions
The heating element set is powered to control the range of heating, and the intensity of heating is controlled by control power.
Preferably, the step heats pail pack 4 specifically: adds to one or several regions of pail pack 4
Heat, heating region are part pail pack 4.Specifically, being heated in the present embodiment to several regions of pail pack 4, including to packaging
The bucket wall of bucket 4, the heating of bucket bottom.The feed way passed through every time with preset volume in the present embodiment, with object (liquid) position of material
It increases, the height for gradually increasing heating region can make radioactivity concentrate thermally equivalent in pail pack 4, help to prevent salt
The highly non-uniform situation of cake occurs.
Preferably, the condition of heating end is carried out to pail pack 4 are as follows: liquid level, solid radiation material in pail pack 4
Moisture content, temperature, delivery temperature, one or several in exhaust steam moisture reach preset requirement condition.When preset requirement condition reaches
After arriving, it can stop heating.It is of course also possible to change with time rule by above-mentioned parameter to determine, certain can also be passed through
Several parameters change with time regular combination to determine, can also be determined by the relationship between above-mentioned parameter.
Specifically, in the present embodiment, when the liquid level in pail pack 4 reaches the 60%~95% of bucket height, object in pail pack 4
Material moisture content reaches 10mas% hereinafter, stopping heating.Preferably, the material of pail pack 4 is thermally conductive metal.Specifically, this
Pail pack 4 in embodiment is steel drum.
(3) by 8 pairs of purification device heating pail pack 4 exhaust (including secondary steam, fixed gas, secondary steam with
Any one in the mixture of fixed gas) gas-liquid separation is carried out, the liquid that gas-liquid separation goes out is flow back into pail pack 4, by gas
The gas that liquid is isolated is passed through condensing unit 9 and is condensed, condensation and separation of liquid be collected into condensate liquid receiving slit 11, lead to
Condensing unit 9 is crossed condensation and separation of fixed gas.Judged in pail pack 4 according to the incrementss of condensate liquid in condensate liquid receiving slit 11
Evaporation capacity, and by metering device 2 to pail pack 4 supplement radioactivity concentrate.Blower 14 and regulating valve 15 cooperate control volume
Tiny structure is tied up to, prevents radgas from leaking.Bung 6 is sealed in evaporation process and bucket ontology 5 seals, and prevents radgas
Leakage.
(4) the solid radiation material in pail pack 4 is dried.
Preferably, the condition of drying end is carried out to the solid radiation material in pail pack 4 are as follows: in pail pack 4
Liquid level, solid radiation material water ratio, temperature, delivery temperature, one or several in exhaust steam moisture reach preset requirement item
Part.
(5) after drying, pail pack 4 is unloaded by jacking apparatus, the pail pack of solid radiation material will be filled
4, it is encased in high integrality container.
The processing method of radioactivity concentrate in the present embodiment uses the operation side of batch processed to radioactivity concentrate
Formula.
The processing method of radioactivity concentrate in the present embodiment, so that the volume reduction ratio of radioactivity concentrate reaches 6~8,
It is 10 times or more of traditional cement curing process (capacity increasing process), the present embodiment is steamed using pail pack 4 as radioactivity concentrate
The container of hair, solid radiation material (such as salt-cake) can be formed directly in the pail pack 4 for being used as packing container, radioactivity
Solid material is packed into high integrality container together with pail pack 4, effectively prevents solid radiation material in cargo handling process
Leakage problem (as generate radioactive dust, aerosol etc.), convenient for the transport and disposition of subsequent solid radiation material, energy
The waste for enough improving nuclear power plant minimizes horizontal, influence of the reduction radioactive solid waste to environment.
It is understood that the principle that embodiment of above is intended to be merely illustrative of the present and the exemplary implementation that uses
Mode, however the present invention is not limited thereto.For those skilled in the art, essence of the invention is not being departed from
In the case where mind and essence, various changes and modifications can be made therein, these variations and modifications are also considered as protection scope of the present invention.
Claims (10)
1. a kind of processing method of radioactivity concentrate, which comprises the following steps:
Radioactivity concentrate is transported in pail pack;
Pail pack is heated, the radioactivity concentrate evaporation in pail pack obtains solid radiation material;
The pail pack of solid radiation material will be filled, is encased in high integrality container.
2. the processing method of radioactivity concentrate according to claim 1, which is characterized in that the step to pail pack into
When row heating, the pressure in pail pack is tiny structure.
3. the processing method of radioactivity concentrate according to claim 1, which is characterized in that the step will fill radiation
Property solid material pail pack, further comprise the steps of: before being encased in high integrality container to the solid radiation object in pail pack
Material is dried.
4. the processing method of radioactivity concentrate according to claim 1, which is characterized in that further comprising the steps of: logical
It crosses purification device and gas-liquid separation is carried out to the exhaust of the pail pack of heating, the liquid that gas-liquid separation goes out is flow back into pail pack, will
The gas that gas-liquid separation goes out is passed through condensing unit and is condensed, to condensation and separation of liquid be collected, pass through condensing unit
Condensation and separation of fixed gas.
5. the processing method of radioactivity concentrate according to claim 1, which is characterized in that the condition of the heating stepses
Are as follows: heating temperature is 50~300 DEG C.
6. the processing method of radioactivity concentrate according to claim 1, which is characterized in that the step to pail pack into
Row heating specifically: one or several regions of pail pack are heated, heating region is part pail pack.
7. the processing method of radioactivity concentrate described in any one according to claim 1~6, which is characterized in that the step
Suddenly radioactivity concentrate is transported in pail pack specifically: radioactivity concentrate is delivered continuously to by packaging by metering device
In bucket, alternatively, by metering device every time in preset volume transportation to pail pack.
8. the processing method of radioactivity concentrate described in any one according to claim 1~6, which is characterized in that the step
Suddenly pail pack is heated specifically: heated by any one in electric heater unit, hot-air, hot oil.
9. the processing method of radioactivity concentrate described in any one according to claim 1~6, which is characterized in that packaging
Bucket carries out the condition of heating end are as follows: liquid level, solid radiation material water ratio, temperature, delivery temperature, exhaust in pail pack
One or several in humidity reach preset requirement condition.
10. the processing method of radioactivity concentrate described in any one according to claim 1~6, which is characterized in that pail pack
Material be thermally conductive metal.
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CN201910717267.5A CN110517803A (en) | 2019-08-05 | 2019-08-05 | The processing method of radioactivity concentrate |
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CN201910717267.5A CN110517803A (en) | 2019-08-05 | 2019-08-05 | The processing method of radioactivity concentrate |
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Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN111128429A (en) * | 2019-12-31 | 2020-05-08 | 西安交通大学 | Drying device and drying method for radioactive concentrated solution in microwave bucket |
CN113539537A (en) * | 2021-08-16 | 2021-10-22 | 成都天保节能环保工程有限公司 | Transferring device and transferring method for radioactive organic waste liquid |
CN115105847A (en) * | 2022-07-04 | 2022-09-27 | 上海核烨工程技术有限公司 | Method and device for drying radioactive concentrated solution in barrel |
CN116153551A (en) * | 2023-01-04 | 2023-05-23 | 中国原子能科学研究院 | Radioactive waste liquid treatment method and system |
Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN107170504A (en) * | 2017-05-25 | 2017-09-15 | 罗杰 | A kind of height ratio puts radioactive wastewater negative pressure evaporation concentrating and treating system and its method |
CN209118786U (en) * | 2018-11-26 | 2019-07-16 | 国家电投集团远达环保工程有限公司重庆科技分公司 | A kind of concentrating and treating system |
-
2019
- 2019-08-05 CN CN201910717267.5A patent/CN110517803A/en active Pending
Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN107170504A (en) * | 2017-05-25 | 2017-09-15 | 罗杰 | A kind of height ratio puts radioactive wastewater negative pressure evaporation concentrating and treating system and its method |
CN209118786U (en) * | 2018-11-26 | 2019-07-16 | 国家电投集团远达环保工程有限公司重庆科技分公司 | A kind of concentrating and treating system |
Non-Patent Citations (5)
Title |
---|
万嘉瑜 等: "桶内干燥技术在放射性废液处理中的应用", 《山东化工》 * |
万嘉瑜 等: "桶内干燥技术在放射性废液处理中的应用"", 《山东化工》 * |
梁栋 等: "放射性废液桶内干燥装置加热方式初步研究", 《环境工程》 * |
梁栋 等: "核电站浓缩液桶内干燥装置的研制及可行性验证", 《辐射防护》 * |
梁栋 等: "模拟浓缩液桶内干燥试验", 《中国核学会核化工分会2014学术交流年会论文集》 * |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN111128429A (en) * | 2019-12-31 | 2020-05-08 | 西安交通大学 | Drying device and drying method for radioactive concentrated solution in microwave bucket |
CN113539537A (en) * | 2021-08-16 | 2021-10-22 | 成都天保节能环保工程有限公司 | Transferring device and transferring method for radioactive organic waste liquid |
CN115105847A (en) * | 2022-07-04 | 2022-09-27 | 上海核烨工程技术有限公司 | Method and device for drying radioactive concentrated solution in barrel |
CN116153551A (en) * | 2023-01-04 | 2023-05-23 | 中国原子能科学研究院 | Radioactive waste liquid treatment method and system |
CN116153551B (en) * | 2023-01-04 | 2024-05-14 | 中国原子能科学研究院 | Radioactive waste liquid treatment method and system |
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Application publication date: 20191129 |