CN103680661B - Nuclear power station solid waste processing system - Google Patents
Nuclear power station solid waste processing system Download PDFInfo
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- CN103680661B CN103680661B CN201310661211.5A CN201310661211A CN103680661B CN 103680661 B CN103680661 B CN 103680661B CN 201310661211 A CN201310661211 A CN 201310661211A CN 103680661 B CN103680661 B CN 103680661B
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Abstract
The invention provides a kind of nuclear power station solid waste processing system, including carrier and be arranged on described carrier for contain cement cementing tank, for contain Calx Calx tank, take for quantitatively dress waste liquid waste liquid measuring tank, take the spent resin measuring tank of spent resin for quantitatively dress, for the stirring of described cement, described Calx, described spent resin and described waste liquid is mixed to form the agitator of mixture, is used for described cement and described Calx being transported to the conveyer in described agitator and being used for containing the pail for used dressings of described mixture；The discharging opening of described cementing tank and described Calx tank connects with the charging aperture of described conveyer respectively, the discharging opening of described conveyer connects with the charging aperture of described agitator, and described waste liquid measuring tank and described spent resin measuring tank connect with the charging aperture of described agitator respectively。The present invention has is easy to mobile, to improve utilization rate beneficial effect。
Description
Technical field
The present invention relates to nuclear power field, particularly relate to a kind of nuclear power station solid waste processing system。
Background technology
Along with nuclear power for civil use technology is increasingly mature, a large amount of uses of new technology new material, operations staff operates the continuous lifting of level in addition, and the yield of nuclear power plant technique radwaste reduces day by day。Nuclear power station solid waste processing system processes manufacturability refuse mainly the kinds of processes modes such as cement solidification。For cement solidification, in 400L metal drum or other container, it is separately added into a number of cement, Calx, additive etc. according to recipe requirements, and add the treated waste such as radioactive resin, then it is made fully to stir well by agitator, mud etc. is utilized to be included in container by radioactivity, to reach the target of fixing nucleic reduction refuse environmental accident risk。
Current new nuclear power station all occurs with the form of four or six " heap groups "。In prior art, two units that mainly have that are comparatively ripe and that be widely adopted share a set of manufacturability solid waste processing system, and every two unit designs share set of system, completely the same and separate between different system。The nuclear power station base that six relatively conventional units are constituted needs this type of system three set altogether。
It is outdated that two commonly used units share a set of nuclear power station solid waste processing system scheme。It is not only bad for reducing Nuclear Power Station cost, and the utilization rate of nuclear power station solid waste processing system is relatively low, and for only having twice or thrice due to year access times, maintenance and the maintenance of system itself also face the challenge。
Summary of the invention
For the defect that the service efficiency of nuclear power station solid waste processing system of the prior art is low, it is provided that the nuclear power station solid waste processing system of a kind of improvement。
This invention address that the technological means that technical problem adopts is: provide a kind of nuclear power station solid waste processing system, including moveable carrier and be arranged on the cementing tank for containing cement on described carrier, for containing the Calx tank of Calx, the waste liquid measuring tank of waste liquid is taken for quantitatively dress, the spent resin measuring tank of spent resin is taken for quantitatively dress, for by described cement, described Calx, described spent resin and the stirring of described waste liquid are mixed into the agitator of mixture, for described cement and described Calx are transported to the conveyer in described agitator, for containing the pail for used dressings of described mixture；
The discharging opening of described cementing tank and described Calx tank connects with the charging aperture of described conveyer respectively, the discharging opening of described conveyer connects with the charging aperture of described agitator, described waste liquid measuring tank and described spent resin measuring tank connect with the charging aperture of described agitator respectively, the inlet communication of the discharging opening of described agitator and described pail for used dressings。
In nuclear power station solid waste processing system provided by the invention, described carrier includes the first vehicular platform, and described cementing tank, described Calx tank and described conveyer are arranged on described first vehicular platform。
In nuclear power station solid waste processing system provided by the invention, described carrier also includes the second vehicular platform, and described waste liquid measuring tank, spent resin measuring tank, described agitator and described pail for used dressings are arranged on described second vehicular platform。
In nuclear power station solid waste processing system provided by the invention, described second vehicular platform is provided with radioprotective container, and described waste liquid measuring tank, spent resin measuring tank, described agitator and described pail for used dressings are arranged in described accommodation chamber。
In nuclear power station solid waste processing system provided by the invention, described carrier also includes the 3rd vehicular platform, described nuclear power station solid waste processing system also includes the lowering or hoisting gear of the charging aperture for the discharge end of described conveyer being raised and is directed at described agitator, and described lowering or hoisting gear is arranged on described 3rd vehicular platform。
In nuclear power station solid waste processing system provided by the invention, described nuclear power station solid waste processing system also includes emergency power supply, and described carrier also includes the 4th vehicular platform, and described emergency power supply is arranged on described 4th vehicular platform。
In nuclear power station solid waste processing system provided by the invention, described conveyer is conveying worm。
In nuclear power station solid waste processing system provided by the invention, described nuclear power station solid waste processing system also includes the holding vessel containing the coagulator for accelerating cement and lime solidification speed, described holding vessel is arranged on described first vehicular platform, and is connected with the charging aperture of described agitator by pipeline。
In nuclear power station solid waste processing system provided by the invention, described nuclear power station solid waste processing system also includes the waste liquid evaporation concentrator for improving liquid waste concentration, described waste liquid evaporation concentrator is arranged on described second vehicular platform, and is connected with described waste liquid measuring tank by pipeline。
Implement nuclear power station solid waste processing system provided by the invention and have the advantages that owing to its all parts is all disposed within above at least one vehicular platform by nuclear power station solid waste processing system provided by the invention, therefore this nuclear power station Solid Waste Treatment can move between multiple units, is therefore easy to the movement of nuclear power station solid waste processing system and improves utilization rate。
Accompanying drawing explanation
Below in conjunction with drawings and Examples, the invention will be further described, in accompanying drawing:
Fig. 1 is the theory diagram of the nuclear power station solid waste processing system in the preferred embodiment of the present invention。
Detailed description of the invention
As it is shown in figure 1, this nuclear power station solid waste processing system is arranged on ground all parts is installed to original on moveable carrier, in order to provide motility and the utilization rate of this nuclear power station solid waste processing system。
This nuclear power station solid waste processing system includes carrier and is arranged on this carrier: for containing the cementing tank 11 of cement, for containing the Calx tank 12 of Calx, the waste liquid measuring tank 13 of waste liquid is taken for quantitatively dress, the spent resin measuring tank 14 of waste liquid is taken for quantitatively dress, for by cement, Calx, spent resin and waste liquid stirring are mixed to form the agitator 15 of mixture, for containing the pail for used dressings 16 of described mixture, for filling the holding vessel 17 of coagulator, for by the conveyer 18 in the cement transportation in the Calx in Calx tank 12 and cementing tank 11 to agitator 15, lowering or hoisting gear and emergency power supply 31。
Owing to this nuclear power station solid waste processing system includes moveable carrier, improve the service efficiency of this nuclear power station solid waste processing system, reduce cost, also solving nuclear power station and meet with the major accident operating mode that the factors such as tsunami are brought out, nuclear power station solid waste processing system wrecks and causes the problem that radioactive liquid waste etc. cannot be quickly obtained effectively process。
Wherein, the discharging opening of Calx tank 12 and the discharging opening of cementing tank 11 dock with the feeding mouth of conveyer 18 respectively, cement and Calx to be discharged to respectively on conveying worm 18。One end being provided with discharging opening of conveyer 18 is removably attached on lowering or hoisting gear, and lowering or hoisting gear adjusts the height of discharging opening one end and the discharging opening of conveyer 18 is connected with the feeding mouth of agitator 15, cement and Calx to be input in agitator 15。
Waste liquid measuring tank 13 connects with the feeding mouth of agitator 15, and its dress takes the waste liquid of predetermined weight or volume and is transported in agitator 15 by this waste liquid；Spent resin measuring tank 14 connects with the feeding mouth of agitator 15, and its dress takes the spent resin of predetermined weight or volume and is transported in agitator 15 by this spent resin。In the present embodiment, the position of waste liquid measuring tank 13 and this spent resin measuring tank 14 is higher than agitator 15, therefore waste liquid measuring tank 13 can connect with this agitator 15 either directly through pipeline with spent resin measuring tank 14, and waste liquid and spent resin are discharged to the feeding mouth of agitator 15 by gravity。
Agitator 15 is positioned at above pail for used dressings 16, the inlet communication of the discharging opening of agitator 15 and pail for used dressings 16, and the stirring mixing of cement, Calx, spent resin, waste liquid and additive is entered in pail for used dressings 16 by agitator 15 by gravity。Emergency power supply 31 is the special power supply of used in nuclear power station, and it is for when running into emergency and causing original power-fail, powering for whole nuclear power station solid waste processing system。
Understandably, cementing tank 11, Calx tank 12, waste liquid measuring tank 13, spent resin measuring tank 14, agitator 15, pail for used dressings 16, holding vessel 17, conveyer 18, lowering or hoisting gear are all identical with the structure of the corresponding component in nuclear power station solid waste processing system of the prior art and principle, therefore repeat no more。
In the present embodiment, all parts interface is designed to insert soon form, whole nuclear power station solid waste processing system quickly can be arranged between nuclear power station difference unit (even different nuclear power bases in region), it is possible to the radioactivity that the indivedual nuclear power station of strategic reply causes due to tsunami etc. processes the environmental disasters such as thrashing
In the present embodiment, this carrier includes the first vehicular platform the 21, second vehicular platform the 22, the 3rd vehicular platform 23 and the 4th vehicular platform 24。Cementing tank 11, Calx tank 12, holding vessel 17 and conveyer 18 are arranged on the first vehicular platform 21。Waste material in waste liquid measuring tank 13, spent resin measuring tank 14, agitator 15 and pail for used dressings 16 has radioactivity。Therefore, waste liquid measuring tank 13, spent resin measuring tank 14, agitator 15 and pail for used dressings 16 are arranged in the radioprotective container of the second vehicular platform 21。Lowering or hoisting gear is arranged on the 3rd vehicular platform 23。Emergency power supply 31 is arranged on the 4th vehicular platform 24。
It is to be appreciated that this conveyer 18 can be conveying worm, cement and lime under agitation in the process of conveying cement and Calx, first can be mixed by conveying worm。
It is to be appreciated that the first vehicular platform 21 is additionally provided with drive motor, this drive motor can provide power for conveying worm 18 and agitator 15。
In another embodiment, the present invention can also increase a waste liquid evaporation concentrator 32 for improving liquid waste concentration on the basis of a upper embodiment。The outlet of this waste liquid evaporation concentrator 32 connects with the entrance of waste liquid measuring tank 13。Its waste liquid produced by nuclear power station unit is flowing to waste liquid measuring tank 13 after concentration。Adopt and first the water in waste liquid is evaporated a part in this way, it is possible to improve the efficiency of nuclear power station solid waste processing system。Owing to the waste liquid in this waste liquid evaporation concentrator 32 has radioactivity, therefore it is also disposed in the accommodation chamber on the second vehicular platform 22。
Should be understood that; above in conjunction with accompanying drawing, embodiments of the invention are described; but the invention is not limited in above-mentioned detailed description of the invention; above-mentioned detailed description of the invention is merely schematic; rather than restrictive, those of ordinary skill in the art is under the enlightenment of the present invention, without departing under present inventive concept and scope of the claimed protection situation; it may also be made that a lot of form, these belong within the protection of the present invention。
Claims (8)
1. a nuclear power station solid waste processing system, it is characterized in that: include moveable carrier and the cementing tank (11) for containing cement being arranged on described carrier, for containing the Calx tank (12) of Calx, the waste liquid measuring tank (13) of waste liquid is taken for quantitatively dress, the spent resin measuring tank (14) of spent resin is taken for quantitatively dress, for by described cement, described Calx, described spent resin and the stirring of described waste liquid are mixed into the agitator (15) of mixture, for described cement and described Calx being transported to the conveyer (18) in described agitator (15), for containing the pail for used dressings (16) of described mixture；
The discharging opening of described cementing tank (11) and described Calx tank (12) connects with the charging aperture of described conveyer (18) respectively, the discharging opening of described conveyer (18) connects with the charging aperture of described agitator (15), described waste liquid measuring tank (13) and described spent resin measuring tank (14) connect with the charging aperture of described agitator (15) respectively, the inlet communication of the discharging opening of described agitator (15) and described pail for used dressings (16)；
Described carrier includes the 3rd vehicular platform (23), described nuclear power station solid waste processing system also includes the lowering or hoisting gear of the charging aperture for the discharge end of described conveyer (18) being raised and is directed at described agitator (15), and described lowering or hoisting gear is arranged on described 3rd vehicular platform (23)。
2. nuclear power station solid waste processing system according to claim 1, it is characterized in that: described carrier includes the first vehicular platform (21), and described cementing tank (11), described Calx tank (12) and described conveyer (18) are arranged on described first vehicular platform (21)。
3. nuclear power station solid waste processing system according to claim 2, it is characterized in that: described carrier also includes the second vehicular platform (22), and described waste liquid measuring tank (13), spent resin measuring tank (14), described agitator (15) and described pail for used dressings (16) are arranged on described second vehicular platform (22)。
4. nuclear power station solid waste processing system according to claim 3, it is characterized in that: described second vehicular platform (22) is provided with radioprotective container, and described waste liquid measuring tank (13), spent resin measuring tank (14), described agitator (15) and described pail for used dressings (16) are arranged in described radioprotective container。
5. nuclear power station solid waste processing system according to claim 1, it is characterized in that: described nuclear power station solid waste processing system also includes emergency power supply (31), described carrier also includes the 4th vehicular platform (24), and described emergency power supply (31) is arranged on described 4th vehicular platform (24)。
6. nuclear power station solid waste processing system according to claim 1, it is characterised in that: described conveyer (18) is conveying worm。
7. nuclear power station solid waste processing system according to claim 2, it is characterized in that: described nuclear power station solid waste processing system also includes containing the holding vessel (17) of the coagulator for accelerating cement and lime solidification speed, described holding vessel (17) is arranged on described first vehicular platform (21), and is connected with the charging aperture of described agitator (15) by pipeline。
8. nuclear power station solid waste processing system according to claim 1, it is characterized in that, described nuclear power station solid waste processing system also includes the waste liquid evaporation concentrator (32) for improving liquid waste concentration, described waste liquid evaporation concentrator (32) is arranged on the second vehicular platform (22), and is connected with described waste liquid measuring tank (13) by pipeline。
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| Application Number | Priority Date | Filing Date | Title |
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| CN201310661211.5A CN103680661B (en) | 2013-12-09 | 2013-12-09 | Nuclear power station solid waste processing system |
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| CN201310661211.5A CN103680661B (en) | 2013-12-09 | 2013-12-09 | Nuclear power station solid waste processing system |
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| CN103680661A CN103680661A (en) | 2014-03-26 |
| CN103680661B true CN103680661B (en) | 2016-06-22 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN105070340B (en) * | 2015-07-17 | 2017-08-04 | 中广核工程有限公司 | A kind of nuclear power plant's solidification of waste processing system and method |
| 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 |
| CN110189846A (en) * | 2019-05-17 | 2019-08-30 | 岭东核电有限公司 | Cement solidification technique and its system |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103366851A (en) * | 2013-07-15 | 2013-10-23 | 中广核工程有限公司 | Cement solidification method for radioactive wet waste |
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| JP3048806B2 (en) * | 1993-10-21 | 2000-06-05 | 株式会社日立製作所 | How to solidify radioactive waste |
| GB2443263B (en) * | 2006-10-26 | 2008-12-24 | Ins Innovation Ltd | Encapsulation of waste for storage |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN103366851A (en) * | 2013-07-15 | 2013-10-23 | 中广核工程有限公司 | Cement solidification method for radioactive wet waste |
Non-Patent Citations (2)
| Title |
|---|
| Treatment of radioactive liquid waste by sorption on natural zeolite in Turkey;Ahmet Erdal Osmanlioglu;《Journal of Hazardous Materials B》;20060306;第332-335页 * |
| 海南昌江核电厂固体放射性废物处理系统技术特点;陈良;《两岸核电废物管理研讨会》;20111012;第137卷;第81-86页 * |
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