CN108257707A - A kind of leaching device for uranium-bearing waste residue - Google Patents
A kind of leaching device for uranium-bearing waste residue Download PDFInfo
- Publication number
- CN108257707A CN108257707A CN201611248681.9A CN201611248681A CN108257707A CN 108257707 A CN108257707 A CN 108257707A CN 201611248681 A CN201611248681 A CN 201611248681A CN 108257707 A CN108257707 A CN 108257707A
- Authority
- CN
- China
- Prior art keywords
- uranium
- waste residue
- feed bin
- cylinder
- bearing waste
- 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.)
- Granted
Links
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
- G21F9/34—Disposal of solid waste
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P10/00—Technologies related to metal processing
- Y02P10/20—Recycling
Abstract
The invention belongs to nuclear fuel cycle technologies, specifically disclose a kind of leaching device for uranium-bearing waste residue, vacuum feeder, caching feed bin, gas separators, bourdon tube cylinder, circular spray tube, cylindrical glass tube and heated cylinder including connecting installation from top to bottom, and the canned motor pump being connect with heated cylinder, canned motor pump send the material in device to next process, the material of bottom of device can also be heated reaction zone bottom, it is stirred, it realizes cycle immixture, while retains the empty stirring of pressure.Increase a vacuum feeding device on cylindrical top to ease up material stock storehouse, uranium-bearing waste residue is promoted in pipeline to the automation of to vacuum feeding device, realizing charging and complete closed using vacuum.During operation, uranium aerosol concentration is less than the requirement of national limit value beside device.Agitating device operational excellence, uranium extraction rate is high, up to more than 99%.Leaching liquid solid content is when 10%, the stirring and mixing effect that has still had.
Description
Technical field
The invention belongs to nuclear fuel cycle technologies, and in particular to a kind of leaching device for uranium-bearing waste residue.
Background technology
During nuclear fuel processing and manufacturing, uranium-bearing waste residue is inevitably resulted from, in Spent Radioactive water process, radioactivity
During combustible waste burns, radioactivity cartridge is reorganized and outfit etc., uranium-bearing waste residue can be also generated, the uranium in these uranium-bearing waste residues contains
Amount is very high, is a big environmental problem if do not handled, there is also criticality safety risks, handle and extract uranium therein not
Only huge social benefit also has very high economic value.It extracts uranium therein and is necessarily required to acidleach process, correspondingly
Need leaching device.
Uranium-bearing waste residue is divided into two classes, and one kind is the waste residue containing natural uranium, and another kind of is the waste residue containing enriched uranium.Containing natural uranium
Waste residue mainly consider to leach effect, radiation protection and leakproofness, the problem of without the concern for criticality safety, leaching device not by
The influence of size, shape, volume can be made very big, select cylindrical tank diameter general in the market, the material selected is done
The leakproofness of good equipment.Waste residue leaching device containing enriched uranium will be considered outside above-mentioned factor, it is contemplated that critical peace
Full problem, i.e. leaching device need safe by geometry, and the shape and size of device are strictly limited, and the requirement of device is high very much.Cause
This, the waste residue leaching device containing enriched uranium can be common to this two classes waste residue.This patent mainly discusses the waste residue leaching containing enriched uranium
Take device.
Existing leaching device is all cylindrical, and device internal diameter is less than 219mm, the high about 4000mm or so of device, due to dress
It puts elongated, is not equipped with mechanical agitation, pressure sky is usually passed through in bottom and carries out auxiliary stirring, charge door is located at the top of cylinder
Portion, top are docked with charging basket, are needed manually to splicing bucket, there is electric heater unit in the lower half of cylinder, it is ensured that temperature control exists
(70~90) DEG C, the exhaust gas for reacting generation is taken away by vacuum, and after having reacted, leaching liquid and insoluble slag are pumped to next hilllock together
Position.There are probelem in two aspects for existing device, first, the problem of stirring, presses the energy force difference of empty stirring, and not tolerant is more in device,
After being deposited on bottom, mixing effect is poor；In leaching process, nitric acid and material reaction can generate big nitrogen carrier of oxygen, add in pressure
Sky then increases exhausted air quantity, has aggravated the burden of washing tail gas, and easily emits slot.Second is that needing to intervene manually, operating personnel need
Frequently charging basket with leaching device to be docked, disconnected, radioactivity material is caused to be exposed in environment, influence the body of operating personnel
Health, it is also bad to environment, it is unsatisfactory for the requirement that country and industry operate radioactive substance.
Invention content
The purpose of the present invention is to provide a kind of leaching devices for uranium-bearing waste residue, can realize the automation of charging
With requirement completely closed, that satisfaction country operates radioactive substance with industry.
Technical scheme is as follows：
A kind of leaching device for uranium-bearing waste residue, the buffering area of charging zone, middle part and the heating of lower end including upper end
Reaction zone, the charging zone include the vacuum feeder, caching feed bin and gas separators of connection, and vacuum feeder is located at top
Portion, interposition caching feed bin are set below vacuum feeder, and gas separators are set below caching feed bin；The gas separators
For a segment pipe, connect with the discharge port of caching feed bin lower end, set on pipeline there are two Pneumatic butterfly valve, two Pneumatic butterfly valves it
Between be equipped with gas feed, gas feed connection nitrogen pipeline；The buffering area includes the cylindrical glass tube of connection, bourdon tube
Cylinder and circular spray tube；The bourdon tube cylinder is spring type cylinder made of elastic material, and upper end is equipped with tail gas
Outlet, bourdon tube cylinder upper end are connect with gas separators lower port so that the two communicates；The circular spray tube is located at
Below bourdon tube cylinder, filling opening is processed on side wall；The cylindrical glass tube is located at below circular spray tube；It is described
Heating reaction zone be located at bottom, including heated cylinder and canned motor pump；The heated cylinder lower end be equipped with sewage draining exit,
Pressure is empty to add in mouth and liquid outlet, and the pressure sky adds in mouth connection pressure vacant duct, and liquid outlet connection canned motor pump is described
The outlet of canned motor pump sets threeway and connects two pipelines, and a pipeline connects subsequent processing, and another pipeline connects heated cylinder.
In a kind of above-mentioned leaching device for uranium-bearing waste residue：The caching feed bin is inverted cone structure,
Small end is downward, and big end is upward, and big end is connected with vacuum feeder lower end discharge port, and caching feed bin is equipped with aerating mouth.
In a kind of above-mentioned leaching device for uranium-bearing waste residue：Electronic scale is equipped in the caching feed bin.
In a kind of above-mentioned leaching device for uranium-bearing waste residue：Sealing is equipped with folder outside the cylindrical glass tube
Tight device.
In a kind of above-mentioned leaching device for uranium-bearing waste residue：Scale is equipped with above the cylindrical glass tube.
In a kind of above-mentioned leaching device for uranium-bearing waste residue：On two pipelines of the outlet of the canned motor pump
Equipped with pneumatic on-off valve.
The remarkable result of the present invention is：
For stirring problem, one canned motor pump of peripheral hardware, the liquid of conveying solid holdup 50%, resistance to 35% nitric acid.This pump
Material in device can be sent to next process, the material of bottom of device can also be heated reaction zone bottom, be stirred
It mixes, realizes cycle immixture, while retain the empty stirring of pressure.
In order to realize the automation of charging and completely closed, the feeding section of leaching device is transformed, on cylindrical top
Increase a vacuum feeding device to ease up material stock storehouse, promoted uranium-bearing waste residue to vacuum feeding device, by true in pipeline using vacuum
Empty loader is put into caching feed bin, and feed bin is equipped with electronic scale, can accurately control feeding quantity, caches between feed bin and extraction column
It is controlled using double butterfly valves, interior inflated with nitrogen, steam in column is avoided to enter caching feed bin, blocks tremie pipe.
Closed conveying and auto feed the arrangement achieves uranium-bearing waste residue do not occur sealing in blanking machine because of vapor
Structure drenches powder, and the thing for blocking tremie pipe is caused to occur.During operation, uranium aerosol concentration is less than national limit value beside device
Requirement.Agitating device operational excellence, uranium extraction rate is high, up to more than 99%.Leaching liquid solid content is when 10%, still
The stirring and mixing effect having had.
Description of the drawings
Fig. 1 is the leaching device schematic diagram for uranium-bearing waste residue；
In figure：1. vacuum feeder；2. cache feed bin；3. gas separators；4. Pneumatic butterfly valve；5. gas feed；6. add
Gas port；7. cylindrical glass tube；8. clamping device；9. bourdon tube cylinder；10. top opening；11. offgas outlet；12. liquid feeding
Mouthful；13. circular spray tube；14. heated cylinder；15. sewage draining exit；16. pressure is empty to add in mouth；17. liquid outlet；18. jettron
Valve；19. canned motor pump；20. pneumatic control valve.
Specific embodiment
Below in conjunction with the accompanying drawings and specific embodiment is described in further detail the present invention.
As shown in Figure 1, the total height of leaching device for uranium-bearing waste residue divides in (5500~6000) mm for three parts, upper end
Charging zone, the buffering area at middle part and the heating reaction zone of lower end.
Charging zone includes vacuum feeder 1, caching feed bin 2 and gas separators 3.
Vacuum feeder 1 is located at top, and interposition caching feed bin 2 is located at 1 lower section of vacuum feeder, gas separators 3
In 2 lower section of caching feed bin.Caching feed bin 2 is inverted vertebral body structure, and small end is downward, and big end is upward.Big end is equipped with interface, with true
Empty 1 lower end discharge port connection of feeder.An aerating mouth 6 is processed at big end, for purging material.
Gas separators 3 are a segment pipe, are connect with the discharge port of 2 lower end of caching feed bin, two gas are installed on pipeline
Dynamic butterfly valve 4, processing gas import 5 between two Pneumatic butterfly valves 4, gas feed 5 connect nitrogen pipeline and are passed through nitrogen, and pass through electricity
Magnet valve controls gas flow, after gas is passed through, forms a sealing gland, completely cuts off the vapor generated due to reaction, acid gas enters
To charging zone, drench material and form blocking.In charging, two Pneumatic butterfly valves 4 open simultaneously, and keep in the material of caching feed bin 2
By gravity downwardly into reaction zone.
Material in automatic charging basket is extracted into eminence come the exhaust gas of generation passes through by vacuum feeder 1 using vacuum from lower
Exhaust system is sent into filtering.The material pumped enters caching feed bin 2 from the bottom of vacuum feeder 1, and caching can pacify in feed bin 2
Electronic scale is filled, after the weight of material in caching feed bin 2 reaches setting value, that is, stops taking out material.
Buffering area includes cylindrical glass tube 7, clamping device 8, bourdon tube cylinder 9 and circular spray tube 13.
Cylindrical glass tube 7 be high 1300mm, the glass tube of diameter 209, above be equipped with scale, for add water or acid when
Time carries out observation use.
Clamping device 8 (clamping cylinder) is sealed and installed with outside cylindrical glass tube 7, effect one is to play sealing function,
Second is that prevent glass from being broken up.
Circular spray tube 13 is installed in 7 top of cylindrical glass tube, and filling opening 12 is processed on side wall, and acid and water add from this mouth
Enter, filling opening is connected with internal circular spray tube, and liquid can flow down along tube wall is past, the material of tube wall capable of washing.
Bourdon tube cylinder 9 is installed above circular spray tube 13, i.e. side wall is spring type cylinder made of elastic material.
The upper end is machined with one section of cone, installs offgas outlet 11 on the circular conical surface of cone, offgas outlet 11 is connected with vacuum pipe, instead
The exhaust gas that should be generated is from the other equipment of this mouthful of entrance.Cone upper end opening is top opening 10, top opening 10 and the gas of charging zone
3 lower port of isolator connects.Bourdon tube cylinder 9 can be expanded with heat and contract with cold with what compensation temperature variation was brought, prevent the cylinder of lower section
Shape glass tube 7 is extruded.
The function of buffering area is acid adding, Jia Shui, takes the exhaust gas that reaction generates away, and is prevented because reacting excessively fierce, generating
The bubbles of a large amount of entrainment materials gush out reaction unit.
Heating reaction zone be located at bottom, including heated cylinder 14 and canned motor pump 19, function be acid and material herein
It is chemically reacted.
Heated cylinder 14 be high 2100mm, the cylinder of diameter 219, material be 316 stainless steels or similar material, cylinder
Heating tape is twined outside body, heating temperature is 50~90 DEG C, and temperature control can be realized by the PLC of device configuration.
14 lower end of heated cylinder is set there are three mouth, and one is sewage draining exit 15, and one is the empty addition mouth 16 of pressure, and one is
Liquid mouth 17.
Pressure is empty to add in the connection pressure vacant duct of mouth 16, sets pneumatic control valve 20 on pipeline, pressure is adjusted by the PLC of device configuration
The flow of sky stirring.Liquid outlet 17 connects canned motor pump 19, and canned motor pump 19 can convey the very high liquid of solid content, canned motor pump 19
Outlet sets threeway, and a pipeline connects subsequent processing, and another back of pipeline heating reaction zone bottom is stirred.Two pipelines
On be respectively mounted pneumatic on-off valve 18, pass through PLC and carry out scene or long-range switching.
Claims (6)
1. a kind of leaching device for uranium-bearing waste residue, the buffering area of charging zone, middle part including upper end and the heating of lower end are anti-
Answer area, it is characterised in that：
The charging zone includes the vacuum feeder (1), caching feed bin (2) and gas separators (3) of connection, vacuum feeder
(1) positioned at top, interposition caching feed bin (2) is below vacuum feeder (1), and gas separators (3) are set on caching feed bin
(2) lower section；The gas separators (3) are a segment pipe, connect with the discharge port for caching feed bin (2) lower end, are set on pipeline
There are two Pneumatic butterfly valve (4), gas feed (5), gas feed (5) connection nitrogen pipeline are equipped between two Pneumatic butterfly valves (4)；
The buffering area includes cylindrical glass tube (7), bourdon tube cylinder (9) and the circular spray tube (13) of connection；Institute
The bourdon tube cylinder (9) stated is spring type cylinder made of elastic material, and upper end is equipped with offgas outlet (11), bourdon tube cylinder
Body (9) upper end is connect with gas separators (3) lower port so that the two communicates；The circular spray tube (13) is positioned at spring
Below pipe cylinder (9), processing filling opening (12) on side wall；The cylindrical glass tube (7) is positioned at circular spray tube
(13) lower section；
The heating reaction zone is located at bottom, including heated cylinder (14) and canned motor pump (19)；The heating cylinder
Body (14) lower end is equipped with the empty addition mouth (16) of sewage draining exit (15), pressure and liquid outlet (17), the pressure sky add in mouth (16) and connect
Vacant duct, the liquid outlet (17) connection canned motor pump (19) are pressed, the outlet of the canned motor pump (19) sets threeway and connects two
Pipeline, a pipeline connect subsequent processing, another pipeline connection heated cylinder (14).
2. a kind of leaching device for uranium-bearing waste residue as described in claim 1, it is characterised in that：The caching feed bin
(2) it is inverted cone structure, small end is downward, and big end is upward, the connection of the same vacuum feeder of big end (1) lower end discharge port, caching
Feed bin (2) is equipped with aerating mouth (6).
3. a kind of leaching device for uranium-bearing waste residue as described in claim 1, it is characterised in that：The caching feed bin
(2) electronic scale is equipped in.
4. a kind of leaching device for uranium-bearing waste residue as described in claim 1, it is characterised in that：The cylindrical glass
It manages sealing outside (7) and is equipped with clamping device (8).
5. a kind of leaching device for uranium-bearing waste residue as described in claim 1, it is characterised in that：The cylindrical glass
It manages (7) and is equipped with scale above.
6. a kind of leaching device for uranium-bearing waste residue as described in claim 1, it is characterised in that：The canned motor pump (19)
Outlet two pipelines on be equipped with pneumatic on-off valve (21).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201611248681.9A CN108257707B (en) | 2016-12-29 | 2016-12-29 | Leaching device for uranium-containing waste residues |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201611248681.9A CN108257707B (en) | 2016-12-29 | 2016-12-29 | Leaching device for uranium-containing waste residues |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN108257707A true CN108257707A (en) | 2018-07-06 |
| CN108257707B CN108257707B (en) | 2023-07-28 |
Family
ID=62721492
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201611248681.9A Active CN108257707B (en) | 2016-12-29 | 2016-12-29 | Leaching device for uranium-containing waste residues |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN108257707B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115404349A (en) * | 2022-09-30 | 2022-11-29 | 中核四0四有限公司 | System and method for recycling metallic uranium in uranium ore indissoluble residues |
Citations (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB428562A (en) * | 1933-04-13 | 1935-05-15 | Krupp Fried Grusonwerk Ag | Process and apparatus for lixiviating ores of precious metals |
| GB813269A (en) * | 1955-01-04 | 1959-05-13 | Commw Scient Ind Res Org | Improvements in and relating to the extraction of uranium |
| JPS589098A (en) * | 1981-06-26 | 1983-01-19 | ウエスチングハウス・エレクトリツク・コ−ポレ−シヨン | Method and device for decreasing volume of heat radioactive liquid waste |
| JPH0332935U (en) * | 1989-08-04 | 1991-03-29 | ||
| CN1177011A (en) * | 1996-09-16 | 1998-03-25 | 宋乐山 | Vertical solid-liquid counter-current extraction column |
| KR20040083462A (en) * | 2003-03-19 | 2004-10-02 | 한국원자력연구소 | Device for metallizing uranium oxide and for recovering the product by filtration |
| KR20090100892A (en) * | 2008-03-21 | 2009-09-24 | 한국원자력연구원 | Aparatus for management chemical waste material |
| RU2484885C1 (en) * | 2012-02-08 | 2013-06-20 | Открытое акционерное общество "Сибирский химический комбинат" | Device for uranium concentrate dissolution |
| CN103711462A (en) * | 2012-10-09 | 2014-04-09 | 核工业北京化工冶金研究院 | Leaching experimental facility for in-situ leaching uranium mining |
| CN103830985A (en) * | 2012-11-20 | 2014-06-04 | 中核建中核燃料元件有限公司 | Filtering system of radioactive dust in vacuum conveying process |
| CN105775779A (en) * | 2014-12-26 | 2016-07-20 | 中核建中核燃料元件有限公司 | Device and method for treating high-fluorine materials |
| CN206421835U (en) * | 2016-12-29 | 2017-08-18 | 中核建中核燃料元件有限公司 | A kind of leaching device for uranium-bearing waste residue |
-
2016
- 2016-12-29 CN CN201611248681.9A patent/CN108257707B/en active Active
Patent Citations (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB428562A (en) * | 1933-04-13 | 1935-05-15 | Krupp Fried Grusonwerk Ag | Process and apparatus for lixiviating ores of precious metals |
| GB813269A (en) * | 1955-01-04 | 1959-05-13 | Commw Scient Ind Res Org | Improvements in and relating to the extraction of uranium |
| JPS589098A (en) * | 1981-06-26 | 1983-01-19 | ウエスチングハウス・エレクトリツク・コ−ポレ−シヨン | Method and device for decreasing volume of heat radioactive liquid waste |
| JPH0332935U (en) * | 1989-08-04 | 1991-03-29 | ||
| CN1177011A (en) * | 1996-09-16 | 1998-03-25 | 宋乐山 | Vertical solid-liquid counter-current extraction column |
| KR20040083462A (en) * | 2003-03-19 | 2004-10-02 | 한국원자력연구소 | Device for metallizing uranium oxide and for recovering the product by filtration |
| KR20090100892A (en) * | 2008-03-21 | 2009-09-24 | 한국원자력연구원 | Aparatus for management chemical waste material |
| RU2484885C1 (en) * | 2012-02-08 | 2013-06-20 | Открытое акционерное общество "Сибирский химический комбинат" | Device for uranium concentrate dissolution |
| CN103711462A (en) * | 2012-10-09 | 2014-04-09 | 核工业北京化工冶金研究院 | Leaching experimental facility for in-situ leaching uranium mining |
| CN103830985A (en) * | 2012-11-20 | 2014-06-04 | 中核建中核燃料元件有限公司 | Filtering system of radioactive dust in vacuum conveying process |
| CN105775779A (en) * | 2014-12-26 | 2016-07-20 | 中核建中核燃料元件有限公司 | Device and method for treating high-fluorine materials |
| CN206421835U (en) * | 2016-12-29 | 2017-08-18 | 中核建中核燃料元件有限公司 | A kind of leaching device for uranium-bearing waste residue |
Non-Patent Citations (2)
| Title |
|---|
| 张建国: "《美国碱法地浸采铀工艺技术概况》", 铀矿冶, no. 1, pages 6 - 13 * |
| 张露;汪萍;黄敏杰;吕彩霞;盛青;孙宏图;滕柯延;: "含铀氟化钙渣的产生控制及清洁解控条件研究", 原子能科学技术, no. 11, pages 1937 - 1942 * |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115404349A (en) * | 2022-09-30 | 2022-11-29 | 中核四0四有限公司 | System and method for recycling metallic uranium in uranium ore indissoluble residues |
| CN115404349B (en) * | 2022-09-30 | 2023-10-27 | 中核四0四有限公司 | Method for recycling metallic uranium in uranium ore indissolvable residues |
Also Published As
| Publication number | Publication date |
|---|---|
| CN108257707B (en) | 2023-07-28 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN101740147B (en) | Dry vertical shaft storage system for spent fuel of nuclear power station and storage method thereof | |
| CN107251156B (en) | Irradiate target processing system | |
| CN203070793U (en) | Shielding transfer device for transporting radioactive waste resin | |
| JP6250651B2 (en) | Method of consolidating radioactive material by hot isostatic pressing (HIP) | |
| CN208622447U (en) | Nuclear power station radioactive spent resin processing unit | |
| JPS6070400A (en) | Method and device for eluting and distributing radioactive nucleus | |
| CN105719712B (en) | A kind of sandwich-type inert gas shielding hot cell | |
| CN104328291A (en) | Oxidizing valence-adjusting equipment for oxidizing Pu (III) to Pu (IV) | |
| CN206421835U (en) | A kind of leaching device for uranium-bearing waste residue | |
| CN108257707A (en) | A kind of leaching device for uranium-bearing waste residue | |
| CN217405118U (en) | Molten salt charging system | |
| GB1036935A (en) | Improvements in or relating to nuclear reactors | |
| CN104851469A (en) | Spiral type whole bucket feeding treatment system | |
| CN216062117U (en) | Automatic separation system for radioactive nuclide | |
| CN206276350U (en) | A kind of reactor solid feeding device | |
| CN106390527B (en) | Explosion-proof type fuel oil dehydration and deoxidation device | |
| CN106373628B (en) | The processing system and method for radioactivity resin | |
| CN217416869U (en) | Recovery unit of gaseous phase material in caprolactam | |
| CN113135545A (en) | Negative pressure type waste resin transport tank car interface system | |
| CN104700916A (en) | Self discharging vertical type Na131I production device | |
| RU121956U1 (en) | INSTALLATION FOR THERMAL DISPOSAL OF RADIOACTIVE-POLLUTED METAL WASTE AND WASTE SOLUTIONS OF TRIBUTILPHOSPHATE IN CARBON, OILS AND OIL PRODUCTS | |
| CN113413928B (en) | Nickel-63 automatic separation device and separation process thereof | |
| NO842671L (en) | DISPOSAL DEVICE FOR METALLURGICAL Ovens | |
| CN104616711A (en) | Self-discharging horizontal type Na131I production device | |
| CN217605397U (en) | Tritium-containing wastewater sampling device for high-temperature gas cooled reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |