CN204792007U - A cask for take up radiant matter - Google Patents
A cask for take up radiant matter Download PDFInfo
- Publication number
- CN204792007U CN204792007U CN201520391127.0U CN201520391127U CN204792007U CN 204792007 U CN204792007 U CN 204792007U CN 201520391127 U CN201520391127 U CN 201520391127U CN 204792007 U CN204792007 U CN 204792007U
- Authority
- CN
- China
- Prior art keywords
- barrel body
- base
- staving
- cask flask
- annular element
- 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.)
- Active
Links
Landscapes
- Processing Of Solid Wastes (AREA)
Abstract
The utility model relates to an equipment relevant with the nuclear radiation material especially relates to a cask for take up radiant matter. Include: a base, the base is circular structure, just be equipped with the step face on the circumference of base. Lower staving, down the staving the bottom with the socket joint is connected between the step face of base. Go up the staving, the vestibule terrace is accepted and is connected between the bottom of going up the staving and the top of time staving. The two -piece type sleeve structure further comprises a top cover, including, be in the same place through cone combined with between the top of top cap and last staving. The radiation that can effectually prevent to be located its inside nuke rubbish bucket like this exceeds standard and causes the influence to operating personnel's health. In addition, to pass through -Modular can effectual reduction occupation space convenient with processing for the container.
Description
Technical field
The utility model relates to a kind of equipment relevant to nuclear radiation material, especially relates to a kind of cask flask for taking up radiant matter.
Background technology
Nuclear power station (nuclearpowerplant) also known as nuclear power plant, be utilize nuclear fission (NuclearFission) or nuclear fusion (NuclearFusion) reaction to discharge energy produce the generating plant of electric energy.Nuclear plant in current business running utilizes nuclear fission react and generate electricity.Nuclear power station is generally divided into two parts: utilize nuclear fission produce the nuclear island (comprising reactor assembly and primary Ioops system) of steam and utilize the conventional island of steam-electric power (comprising steam turbine generator system), the fuel of use is generally radioactivity heavy metal: uranium, plutonium.
Nuclear energy power plant can produce low-order and high-order radioactive waste, or used nuclear fuel, although volume is little, because having radioactive ray, therefore must be prudent in dealing with.The nuclear energy power generation of present stage, still can produce a lot of radioactive waste, wherein especially with the process of high-level waste and dispose as an international difficult problem.
Current nuclear power plant solid waste processing system adopts dry cement and adjuvant spent resin and concentrate to be solidificated in 400L steel drum, to carry out permanent disposal, prevents radiomaterial from spreading.When the 400L steel drum surface dose rate filling refuse carries out transporting in factory more than 2mSv/h, need shield steel drum, guarantee that outside surface dose rate is no more than 2mSv/h after shielding.
Summary of the invention
Task of the present utility model is to provide one can take up nuke rubbish steel drum, and the container making final surface emissivity dosage up to standard.This container comprises: a base, the rounded structure of described base, and described base be circumferentially provided with step surface.Lower barrel body, between the bottom of described lower barrel body and the step surface of described base, socket joint is connected.Upper barrel body, is connected by step surface socket joint between the bottom of described upper barrel body and the top of lower barrel body.One top cover, passes through together with cone match between described top cover and the top of upper barrel body.
Further be improved to, the junction of described cask flask is integral by being welded to connect.
Further be improved to, the outer circumference surface of described upper barrel body be fixedly installed annular element one, the outer circumference surface of described lower entire body is fixedly installed annular element two.
Further be improved to, the outer most edge of described annular element one and annular element two is equal to the distance of base central axis.
Further be improved to, the upper end of described top cover is provided with suspension ring.
Further be improved to, the surfaces externally and internally of the cask flask be made up of described base, lower barrel body, upper entire body, top cover is coated with radiation shielding coating layer.
Can effectively prevent from the radiation of the nuclear waste barrel being positioned at its inside from exceeding standard like this to impact the health of operating personnel.In addition, container effectively can be reduced by block combiner and to take up room and easy to process.
Accompanying drawing explanation
Fig. 1 is taken up the side view of container;
Fig. 2 is that utility model is for taking up the structural representation of an embodiment of the cask flask of radiant matter;
Fig. 3 is the cut-open view taking up the cask flask of container in Fig. 2.
Description of reference numerals:
1-suspension ring one, 2-staving, 10-base, 20-lower barrel body, 22-annular element two, 30-upper barrel body, 32-annular element one, 40-top cover, 50-suspension ring.
Embodiment
Contrast accompanying drawing below, by the description to embodiment, the effect of the mutual alignment between the shape of each component involved in embodiment of the present utility model, structure, each several part and annexation, each several part and principle of work etc. are described in further detail.
400L steel drum as shown in Figure 1, this steel drum is made up of staving 2 and the suspension ring 1 being positioned at staving top, is mainly used in the radiativity waste material directly taken up in nuclear power station.Shown in Fig. 2,3 is cask flask for taking up trash receptacle shown in Fig. 1.The cylindrical structure of this container, it is spliced by base 10, lower barrel body 20, upper barrel body 30, top cover 40, complete splice and combine after junction is integrally welded.
This base 10 be circumferentially provided with step surface, for and lower barrel body 20 excircle on step surface between socket joint connect.Also be provided with step surface at the other end of lower entire body 20 to be connected by step surface socket joint with the bottom of relative upper barrel body 30.Be processed into expanding structure in upper barrel body 30 inner chamber upper port, linked together by cone match between the top reaming of top cover 40 and upper barrel body 30.
Because upper lower barrel body is all annular element, such structure is not easy to carry out lifting assembling.Lift for the ease of upper lower barrel body, the excircle of upper barrel body 30 is fixedly installed annular element 1, the excircle of lower barrel body 20 is fixedly installed annular element 2 22.Time simultaneously in order to prevent the cask flask side welded from rotating, being uneven due to annular element 1 and annular element 2 22 thus making trash receptacle severe jolt in container.So the outer most edge of annular element 1 and annular element 2 22 is set as identical to the distance of base 10 central axis in the present embodiment.Stable movement when side rotates can be ensured like this.
For the ease of handling, so be provided with the suspension ring 50 more consistent with suspension ring 1 structure above top cover 40.On the surfaces externally and internally of cask flask, be coated with radiation shielding coating layer simultaneously.Can effectively reduce radiation like this to leak.Certainly, the specification of cask flask can do adaptability design according to the specification of trash receptacle, and is not limited to cylindrical structural.
Claims (6)
1. for taking up a cask flask for radiant matter, it is characterized in that, comprising:
One base (10), described base (10) rounded structure, and described base (10) be circumferentially provided with step surface;
Lower barrel body (20), between the bottom of described lower barrel body (20) and the step surface of described base (10), socket joint is connected;
Upper barrel body (30), is connected by step surface socket joint between the bottom of described upper barrel body (30) and the top of lower barrel body (20);
One top cover (40), described top cover (40) passes through together with cone match between the top of upper barrel body (30).
2. cask flask as claimed in claim 1, is characterized in that: the junction of described cask flask is integral by being welded to connect.
3. cask flask as claimed in claim 1 or 2, is characterized in that: the outer circumference surface of described upper barrel body (30) is fixedly installed annular element one (32), the outer circumference surface of described lower barrel body (20) is fixedly installed annular element two (22).
4. cask flask as claimed in claim 3, is characterized in that: the outer most edge of described annular element one (32) and annular element two (22) is equal to the distance of base (10) central axis.
5. cask flask as claimed in claim 4, is characterized in that: the upper end of described top cover (40) is provided with suspension ring (50).
6. cask flask as claimed in claim 5, is characterized in that: the surfaces externally and internally of the cask flask be made up of described base (10), lower barrel body (20), upper entire body (30), top cover (40) is coated with radiation shielding coating layer.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520391127.0U CN204792007U (en) | 2015-06-09 | 2015-06-09 | A cask for take up radiant matter |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520391127.0U CN204792007U (en) | 2015-06-09 | 2015-06-09 | A cask for take up radiant matter |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN204792007U true CN204792007U (en) | 2015-11-18 |
Family
ID=54532008
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201520391127.0U Active CN204792007U (en) | 2015-06-09 | 2015-06-09 | A cask for take up radiant matter |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN204792007U (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106895995A (en) * | 2017-03-13 | 2017-06-27 | 四川行之智汇知识产权运营有限公司 | Reactor boron concentration samples corollary equipment |
| CN107644692A (en) * | 2017-09-30 | 2018-01-30 | 中国核电工程有限公司 | A kind of novel locating device |
-
2015
- 2015-06-09 CN CN201520391127.0U patent/CN204792007U/en active Active
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106895995A (en) * | 2017-03-13 | 2017-06-27 | 四川行之智汇知识产权运营有限公司 | Reactor boron concentration samples corollary equipment |
| CN107644692A (en) * | 2017-09-30 | 2018-01-30 | 中国核电工程有限公司 | A kind of novel locating device |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN103106938B (en) | A kind of spent fuel transport container with damping, protecting against shock spring assembly | |
| CN204792007U (en) | A cask for take up radiant matter | |
| JP6695948B2 (en) | Radioactive waste container | |
| CN207765180U (en) | Nuclear power plant's radwaste safe transit cask flask | |
| CN205428505U (en) | A shielding transport vechicle for transporting nuclear power station solid waste bucket | |
| CN203931524U (en) | Radioactive solid waste bucket | |
| Wimmer et al. | Castor® and Constor®: A well established system for the dry storage of spent fuel and high level waste | |
| CN207947074U (en) | Screening arrangement | |
| JP5634924B2 (en) | Method for tailoring radioactive material transport storage container and lid auxiliary shield for tailoring work | |
| US20150092903A1 (en) | Method and container packaging and transporting irradiated control rod blades | |
| CN207503651U (en) | A kind of novel locating device | |
| CN107644692A (en) | A kind of novel locating device | |
| CN203733484U (en) | Shielding transshipment container in main-pump hydraulic component factory | |
| CN207381102U (en) | A kind of container for transporting radioactive substance | |
| CN109727697B (en) | High-radioactivity waste receiving device | |
| JP6338343B2 (en) | Radioactive material storage container | |
| Baeg et al. | Development of the Vacuum Drying Process for the PWR Spent Nuclear Fuel Dry Storage | |
| CN204991164U (en) | Neutron source shipping container | |
| CN208433226U (en) | A kind of npp safety shell filtering emission system | |
| CN214752976U (en) | Transfer container in spent fuel plant | |
| Dietrich et al. | Decommissioning of the thorium high temperature reactor (THTR 300) | |
| CN204166909U (en) | A kind of spent fuel dry-type storage device | |
| CN207217126U (en) | The waste and old neutron probe storage and transportation apparatus of RIC systems | |
| CN208111102U (en) | A kind of storage container after detector containing high-enriched uranium is retired | |
| Howard et al. | Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant |