CN203673837U - Radwaste solidified body containing container - Google Patents
Radwaste solidified body containing container Download PDFInfo
- Publication number
- CN203673837U CN203673837U CN201320722928.1U CN201320722928U CN203673837U CN 203673837 U CN203673837 U CN 203673837U CN 201320722928 U CN201320722928 U CN 201320722928U CN 203673837 U CN203673837 U CN 203673837U
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- China
- Prior art keywords
- radwaste
- sample
- solidification
- casing
- container
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- 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.)
- Expired - Lifetime
Links
- 238000007711 solidification Methods 0.000 claims description 17
- 230000008023 solidification Effects 0.000 claims description 17
- 239000000725 suspension Substances 0.000 claims description 4
- 238000001514 detection method Methods 0.000 abstract description 5
- 238000012360 testing method Methods 0.000 abstract description 5
- 230000005855 radiation Effects 0.000 abstract 1
- 239000000523 sample Substances 0.000 description 23
- 238000013461 design Methods 0.000 description 10
- 230000002285 radioactive effect Effects 0.000 description 10
- 238000000034 method Methods 0.000 description 5
- 239000004568 cement Substances 0.000 description 4
- 230000000694 effects Effects 0.000 description 3
- 238000004806 packaging method and process Methods 0.000 description 3
- 239000002699 waste material Substances 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 238000000151 deposition Methods 0.000 description 2
- 238000011056 performance test Methods 0.000 description 2
- 238000002360 preparation method Methods 0.000 description 2
- 238000003860 storage Methods 0.000 description 2
- 230000032258 transport Effects 0.000 description 2
- 239000010963 304 stainless steel Substances 0.000 description 1
- 229910000589 SAE 304 stainless steel Inorganic materials 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 230000001771 impaired effect Effects 0.000 description 1
- 239000006101 laboratory sample Substances 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 239000002910 solid waste Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
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Abstract
The utility model discloses a radwaste solidified body containing container which comprises a box body (1). A box door (2) is arranged on the side face of the box body (1), a plurality of layers of grids (3) are arranged in the box body (1), and a plurality of drawers (4) used for containing solidified body samples (10) are arranged on each layer of grids (3). The box body and the box door are of a dual-wall structure, and the space between every two walls is filled with a lead layer (5). According to the technical scheme, it is guaranteed that the solidified body samples can be conveyed to a performance detection test destination safely and completely, the container can be used for temporally storing samples for tests, and radiation on personnel is reduced.
Description
Technical field
The utility model belongs to transportation and the storage field of radioactive solid waste, is specifically related to a kind of low, middle Intermediate Level Radioactive solidification of waste body container containing.
Background technology
So far, low, middle Intermediate Level Radioactive refuse adopts traditional cement solidification/technique for fixing to process, for guaranteeing interim storage and the final disposal safety of refuse, the solidify/fixing refuse body producing need carry out Performance Detection and assessment, to meet relevant national standard requirement." low, middle Intermediate Level Radioactive solidification of waste body performance requirement solidified cement body " (GB14569.1-2011) stipulated performance requirement and the detection method of radioactive waste solidified cement body, and standard recommendation adopts the curing sample of φ 50mm × 50mm to carry out Performance Detection test.
The preparation that radioactivity is solidified sample can complete in laboratory, and the preparation of laboratory sample need to be consistent with curing curing formula and the curing process that generates line of unit of operation as far as possible.Another effective way of obtaining sample is to generate line and directly gather from cement solidification, and the sample of collection at the scene maintenance is full after 28 days, transports laboratory to and carries out performance test and assessment.
In order to ensure the validity of performance test results, need meet 3 requirements by the transportation of solidifying generation line collection in worksite sample: (1) has enough shielding measures; (2) anticollision design, prevents that sample from affecting Performance Evaluation result because transporting breakage; (3) be convenient to placement and the recovery of sample.
Utility model content
For guaranteeing that sample meets above-mentioned requirement, the utility model provides a kind of solidification of radwaste body container containing, can guarantee firming body secure sample, intactly transport Performance Detection test objective to; Can be used for temporarily depositing of test specimen, reduce personnel's radioactive dose.
For reaching above object, the technical solution adopted in the utility model is: a kind of solidification of radwaste body container containing is provided, comprises casing, the side of described casing is provided with chamber door, in described casing, be provided with multilayer grid, every layer of described grid is provided with multiple drawers for splendid attire firming body sample; Described casing and chamber door are double-wall structure, between described double wall, fill lead layer.
Further, the bottom of described casing is provided with footing, and the top of described casing is provided with suspension ring.
Further, described drawer is provided with handle.
Useful technique effect of the present utility model is:
(1) specificity of container.This container designs for the regulation of GB14569.1-2011, can meet the transportation of sample and the requirement of depositing;
(2) Optimal Structure Designing of container.This container is side opening door type structure, between casing and chamber door, is provided with door lock, guarantees the safety of refuse transportation; Internal tank is stratiform drawer-type structure, can layering carries out placement and the reclaimer operation of sample, effectively reduces operating personnel's radioactive dose; Every layer is grill designs, and each grid is placed a kind of sample, can prevent the breakage that the collision in transportation causes, guarantees integrality and the trackability of sample;
(3) shielding of container design.Casing and chamber door are double-wall structure, fill lead layer in double wall, and effectively minimizing personnel are shone.
Accompanying drawing explanation
Fig. 1 is the utility model solidification of radwaste body packaging container vertical view cutaway drawing;
Fig. 2 is that the utility model solidification of radwaste body packaging container master looks cut-open view;
Fig. 3 is the utility model solidification of radwaste body packaging container drawer, grid schematic diagram.
In figure:
1-casing 2-chamber door 3-grid 4-drawer 5-lead layer
6-footing 7-suspension ring 8-door lock 9-turning axle 10-firming body sample
11-handle
Embodiment
Below in conjunction with accompanying drawing, embodiment of the present utility model is described in further detail.
As Figure 1-3, the solidification of radwaste body container containing that the utility model provides, for the transportation of low, Intermediate Level Radioactive solidification of waste body with deposit temporarily.Comprise casing 1, a side of described casing 1 is provided with chamber door 2, and casing is connected by turning axle 9 with chamber door, is provided with door lock 8 on casing and chamber door, can guarantee the safety in refuse transportation; In casing 1, be provided with multilayer grid 3, every layer of grid 3 is provided with multiple drawers 4 for splendid attire firming body sample 10, and each drawer 4 is provided with handle 11; Casing 1 and chamber door 2 are double-wall structure, fill lead layer 5 in double wall, can reduce a staff and be shone.The bottom of casing is provided with footing 6, avoids the bottom of container impaired; The top of casing is provided with suspension ring 7, is convenient to lifting.
Adopt this structure, firming body sample 10 can be carried out to layering placement and reclaimer operation, can effectively reduce operating personnel's radioactive dose.Wherein, every layer of grid placed a firming body sample, and grid size designs with reference to the size of sample solidifies standard die trial, when sample transportation, can be with die trial to place.Adopt this design can prevent well the breakage causing due to the collision in transportation, guarantee integrality and the trackability of firming body sample.
Now be described below for design, the procedure of processing of solidification of radwaste body container containing:
Describe take the firming body sample of φ 50mm × 50mm as splendid attire object.External container size is made as 540mm × 492mm × 630mm, the high 80mm that is made as of footing.Container adopts double-wall structure, and every layer of wall thickness is thick 304 corrosion resistant plates of 5mm, fills 60mm lead layer between double wall.Internal tank adopts stratiform drawer-type structure, and totally seven layers, the drawer on every layer of grid can be placed 20 firming body samples 10, puts altogether 140 samples.Grid adopts 4#304 stainless steel angle steel, and drawer main body adopts thick 304 corrosion resistant plates of 3mm, can meet request for utilization.
About the design of shielding, more with content in low, middle Intermediate Level Radioactive refuse, relatively typical Co-60, Cs-137 and tri-kinds of radioactive nuclides of Sr-90 are the shielding design that container is carried out in source item input, source item has adopted the high radioactivity level of each nucleic, lead thickness meets cask requirement take vessel surface dosage and calculates as benchmark, the lead layer that protection equivalent is 60mm.In addition, also to take into full account nucleic activity concentration in single sample and the total activity of all splendid attire samples when design.
Solidification of radwaste body container containing of the present utility model, is not limited to above-mentioned embodiment, and those skilled in the art draw other embodiment according to the technical solution of the utility model, belongs to equally technological innovation scope of the present utility model.
Claims (3)
1. a solidification of radwaste body container containing, comprise casing (1), the side of described casing (1) is provided with chamber door (2), it is characterized in that: in described casing (1), be provided with multilayer grid (3), every layer of described grid (3) is provided with multiple drawers (4) for splendid attire firming body sample (10); Described casing and chamber door are double-wall structure, fill lead layer (5) between described double wall.
2. solidification of radwaste body container containing as claimed in claim 1, is characterized in that: the bottom of described casing (1) is provided with footing (6), the top of described casing (1) is provided with suspension ring (7).
3. solidification of radwaste body container containing as claimed in claim 1, is characterized in that: described drawer (4) is provided with handle (11).
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201320722928.1U CN203673837U (en) | 2013-11-15 | 2013-11-15 | Radwaste solidified body containing container |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201320722928.1U CN203673837U (en) | 2013-11-15 | 2013-11-15 | Radwaste solidified body containing container |
Publications (1)
Publication Number | Publication Date |
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CN203673837U true CN203673837U (en) | 2014-06-25 |
Family
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Family Applications (1)
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CN201320722928.1U Expired - Lifetime CN203673837U (en) | 2013-11-15 | 2013-11-15 | Radwaste solidified body containing container |
Country Status (1)
Country | Link |
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CN (1) | CN203673837U (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109874299A (en) * | 2015-04-17 | 2019-06-11 | 依诺维公司 | Method for encapsulating radioactive waste |
CN110060791A (en) * | 2019-06-05 | 2019-07-26 | 程兵 | It is a kind of for storing the decaying device of useless radioactive particle bracket |
CN110570968A (en) * | 2017-12-28 | 2019-12-13 | 中核四0四有限公司 | Cement fixed steel box grating for intermediate solid waste |
-
2013
- 2013-11-15 CN CN201320722928.1U patent/CN203673837U/en not_active Expired - Lifetime
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109874299A (en) * | 2015-04-17 | 2019-06-11 | 依诺维公司 | Method for encapsulating radioactive waste |
CN110570968A (en) * | 2017-12-28 | 2019-12-13 | 中核四0四有限公司 | Cement fixed steel box grating for intermediate solid waste |
CN110060791A (en) * | 2019-06-05 | 2019-07-26 | 程兵 | It is a kind of for storing the decaying device of useless radioactive particle bracket |
CN110060791B (en) * | 2019-06-05 | 2022-12-30 | 程兵 | Decay device for storing waste radioactive particle support |
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Price | On-Line Waste Library Supporting Information |
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Date | Code | Title | Description |
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C14 | Grant of patent or utility model | ||
GR01 | Patent grant | ||
CX01 | Expiry of patent term | ||
CX01 | Expiry of patent term |
Granted publication date: 20140625 |