CN201956081U - Shielding transferring device for radioactive substance - Google Patents
Shielding transferring device for radioactive substance Download PDFInfo
- Publication number
- CN201956081U CN201956081U CN2010206610802U CN201020661080U CN201956081U CN 201956081 U CN201956081 U CN 201956081U CN 2010206610802 U CN2010206610802 U CN 2010206610802U CN 201020661080 U CN201020661080 U CN 201020661080U CN 201956081 U CN201956081 U CN 201956081U
- Authority
- CN
- China
- Prior art keywords
- end cover
- baffle plate
- locking pin
- shielding
- welded
- 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.)
- Expired - Lifetime
Links
Images
Abstract
The utility model discloses a shielding transferring device for radioactive substance, which comprises an upper end cover, a lower end cover, a barrel body, a lead shielding layer, a safety locking mechanism, a joint butt and a position indicator. The shielding transferring device for the radioactive substance can achieve the long-distance operation of a highly radioactive substance in a whole air dry-type transferring process, automatical guide centered, is simple, reliable and feasible to operate, greatly improves work efficiency, effectively solves the technical difficult problems that the radiation protection and the butt joint of a spent fuel assembly in an air transferring process are difficult, the operation difficulty is large and the like, reduces the unnecessary radiation damage to workers, and can ensure the radiation safety of the workers and the safety of the highly radioactive substance in the transferring process.
Description
Technical field
The utility model relates to a kind of shield assembly of radiomaterial, is specifically related to be used for the spentnuclear fuel of the operation of aerial dry type transhipment nuclear facilities, retired process, the radiomaterial shielding transporter of the contour radiomaterial of radioactive source.
Background technology
For guaranteeing nuclear facilities, nuclear material and environmentAL safety, in the contour radiomaterial outward transport of irradiated fuel assembly, radioactive source permanent storage process, pond etc. is interim to store the place or interim reservoir vessel is transported to the dedicated storage container or special-purpose cask carries out tinning from preserving with it must to take shielding measure.Because facility and place restriction can't realize the transhipment of the shielding wet type under water tinning of irradiated fuel assembly, the contour radiomaterial of radioactive source, effective workaround is exactly to adopt the shielding transporter that can realize aerial dry type transhipment.Present shielding transporter when the high radioactivity substance transportation imports the shielding transporter, be difficult in and centering; The high radioactivity material imports shielding transporter and tinning complex operation, and workload is big; The high radioactivity material imports the shielding transporter and tinning is leaned on manually closely manual operation more, and radiation has a big risk.
Summary of the invention
The purpose of this utility model is: a kind of energy automatic guide centering is provided, and row simple to operate, reliable, easy, can guarantee that the radiomaterial of staff's radiation safety shields transporter.
The utility model is achieved in that
A kind of radiomaterial shielding transporter, comprise and be welded with the upper end cover that shackle shaft, top center have the instrument manhole appendix, between upper end cover and bottom end cover, has the lead shield layer, the two ends up and down of cylindrical shell cooperate with upper end cover and bottom end cover butt joint respectively, upper end cover, bottom end cover and cylindrical shell are integrally welded, it is characterized in that: described shielding transporter is provided with position indicator on upper end cover; Cylindrical shell has inside and outside two-layer; The internal diameter of bottom end cover is identical with the internal diameter of cylindrical shell internal layer, lower end and butt junction taper fit; Butt junction is welded on the bottom of bottom end cover and connects by coupling bolt; Safety locking mechanism is welded on the cylindrical shell by fixed head.
Its supplementary features are:
Described safety locking mechanism is made up of locking pin, locking pin upper limit plate, locking pin stopper slot, fixed head, baffle plate, locking pin lower limiting board, the spacing guide finger of baffle plate and baffle plate lever; The upper surface symmetry of baffle plate is milled with two blind recess; The upper end of the spacing guide finger of baffle plate is fixed on the fixed head by nut, is welded with locking pin upper limit plate on the fixed head, and locking pin places in the locking pin stopper slot; The outer face of baffle plate is welded with the baffle plate lever.
Described butt junction is circular, and its top has groove, and the inner chamber lower end is a tapering, with bottom end cover be taper fit, a straight ring section coaxial with the instrument manhole appendix arranged between the double tapered.
Effect of the present utility model is: radiomaterial shielding transporter of the present utility model, as irradiated fuel assembly in-out apparatus passage, safety locking mechanism has guaranteed that device in the transport process effectively contains the integrality of irradiated fuel assembly with the opening of butt junction and bottom end cover double tapered guiding; Providing convenience for remote lifting irradiated fuel assembly hanging basket as irradiated fuel assembly gripping tool passage in upper end cover top center hole, effectively reduces radioactive dose in staff's operation process, reduced the unnecessary radiation injury of staff; Under the prerequisite that guarantees the radiation protection shielding, can realize the remote-controlled operation of the aerial dry type transhipment of high radioactivity material overall process, automatic guide centering, and row simple to operate, reliable, easy greatly provide work efficiency; The utility model can be guaranteed the safety of high radioactivity material in staff's radiation safety and the transport process.
Description of drawings
Fig. 1 is a structural representation of the present utility model.
Fig. 2 is the butt junction structural representation.
Fig. 3 is the safety locking mechanism structural representation.
Fig. 4 is the left view of Fig. 3.
Fig. 5 is the vertical view of Fig. 3.
Among the figure: 1. shackle shaft; 2. position indicator; 3. instrument manhole appendix; 4. upper end cover; 5. lead shield layer; 6. cylindrical shell; 7. bottom end cover; 8. butt junction; 9. safety locking mechanism; 10. locking pin; 11. locking pin upper limit plate; 12. locking pin stopper slot; 13. groove; 14. register pin; 15. coupling bolt; 16. fixed head; 17. baffle plate; 18. locking pin lower limiting board; 19. nut; 20. the spacing guide finger of baffle plate; 21. baffle plate lever; 22. blind recess; 23. straight ring section.
Embodiment
Shielding transporter of the present utility model is made up of position indicator 2, upper end cover 4, lead shield layer 5, cylindrical shell 6, bottom end cover 7, butt junction 8 and safety locking mechanism 9 as shown in Figure 1.
Upper end cover 4 is opened two hanger axis holes circumferentially uniform, and shackle shaft 1 adopts clearance fit with upper end cover 4, is welded on after the installation on the upper end cover 4; Upper end cover 4 top center have the instrument manhole appendix 3 for the turnover of irradiated fuel assembly gripping tool; Upper end cover 4 is provided with position indicator 2, and position indicator 2 can confirm conveniently that irradiated fuel assembly enters shielding transporter inside and whether puts in place; Cylindrical shell 6 has inside and outside two-layer, has lead shield layer 5 between upper end cover 3 and the bottom end cover 7; Upper end cover 4, bottom end cover 7 and cylindrical shell 6 are integrally welded; It between upper end cover 4, bottom end cover 7 and the cylindrical shell 6 space of containing the contour radiomaterial of spent fuel element; Bottom end cover 7 is circular, and the top internal diameter is identical with cylindrical shell 6 internal layer internal diameters, lower end and butt junction 8 taper fit.
Butt junction 8 as shown in Figure 2, butt junction 8 be a ring texture with bottom end cover 7, overall co-ordination is a double tapered, and a straight ring section 23 coaxial with instrument manhole appendix 3 arranged between the double tapered, can guarantee that irradiated fuel assembly turnover shielding transporter is not subjected to jam and realization is automatic to locate; Butt junction 8 is welded on the bottom of bottom end cover 7 and connects by coupling bolt hole 15 usefulness nuts, has groove 13 at the top of butt junction 8.
Safety locking mechanism 9 is made up of locking pin 10, locking pin upper limit plate 11, locking pin stopper slot 12, fixed head 16, baffle plate 17, locking pin lower limiting board 18, the spacing guide finger 20 of baffle plate and baffle plate lever 21 as Fig. 3, Fig. 4, shown in Figure 5.Safety locking mechanism 9 integral body are welded on the cylindrical shell 6 by fixed head 16, the upper surface symmetry of baffle plate 17 is milled with two blind recess 22, pull out and insert the moving conduit of the spacing guide finger 20 of baffle plate as baffle plate 17, end face by spacing guide finger 20 of pin baffle plate and groove 22 is spacing, prevents that plate washer 17 from pulling out landing; The upper end of the spacing guide finger 20 of baffle plate is fixed on the fixed head 16 with nut 19, is welded with locking pin upper limit plate 11 on the fixed head 16, and locking pin 10 places in the locking pin stopper slot 12, can realize the release and the locking of baffle plate 17.Baffle plate 17 outer faces are welded with baffle plate lever 21, can realize extracting out and insertion baffle plate 17 with the long handle instrument is remote; The baffle plate 17 of safety locking mechanism 9 can level move back and forth in the groove 13 of butt junction 8, and groove 13 and baffle plate 17 can guarantee fully to dewater before the aerial transhipment of irradiated fuel assembly, realize the dry type transhipment.Safety locking mechanism 9 can utilize its locking device realization baffle plate 17 to extract and insert dibit locking out, prevents the irradiated fuel assembly case accident and irradiated fuel assembly is included in its structural intergrity of maintenance in the shielding transporter.
When the aerial dry type of irradiated fuel assembly was transported, radiomaterials such as the irradiated fuel assembly of packing into from upper end cover 4 grasped specific purpose tool; With crane top, preservation pond is arrived in the utility model handling, opened safety locking mechanism 9; Grasp irradiated fuel assembly under water with instrument, enter in the cylindrical shell 6 from butt junction 8 and bottom end cover 7, confirm that by the position indicator on the upper end cover 42 irradiated fuel assemblies enter cylindrical shell 6 inside fully after, lock and dewater with safety locking mechanism 9; Integral body lifts to the tinning place from aerial then, dock with spent fuel transport container by butt junction 8, after finishing, butt joint opens safety locking mechanism 9, decline irradiated fuel assembly gripping tool, irradiated fuel assembly is imported spent fuel transport container from the utility model lower end passage, finish the aerial dry type transhipment of radiomaterials such as irradiated fuel assembly.Overall process all is remote-controlled operations.
Claims (3)
1. a radiomaterial shields transporter, comprise and be welded with the upper end cover (4) that shackle shaft (1), top center have instrument manhole appendix (3), between upper end cover (4) and bottom end cover (7), has lead shield layer (5), the two ends up and down of cylindrical shell (6) cooperate with upper end cover (4) and bottom end cover (7) butt joint respectively, upper end cover (4), bottom end cover (7) and cylindrical shell (6) are integrally welded, it is characterized in that: described shielding transporter is provided with position indicator (2) on upper end cover (4); Cylindrical shell (6) has inside and outside two-layer; The internal diameter of bottom end cover (7) is identical with the internal diameter of cylindrical shell (6) internal layer, lower end and butt junction (8) taper fit; Butt junction (8) is welded on the bottom of bottom end cover (7) and connects by coupling bolt (15); Safety locking mechanism (9) is welded on the cylindrical shell (6) by fixed head (16).
2. according to the described radiomaterial shielding of claim 1 transporter, it is characterized in that: described safety locking mechanism (9) is made up of locking pin (10), locking pin upper limit plate (11), locking pin stopper slot (12), fixed head (16), baffle plate (17), locking pin lower limiting board (18), the spacing guide finger of baffle plate (20) and baffle plate lever (21); The upper surface symmetry of baffle plate (17) is milled with two blind recess (22); The spacing guide finger of baffle plate (20) is fixed on the fixed head (16) by nut (19), is welded with locking pin upper limit plate (11) on the fixed head (16), and locking pin (10) places in the locking pin stopper slot (12); The outer face of baffle plate (17) is welded with baffle plate lever (21).
3. according to the described radiomaterial shielding of claim 1 transporter, it is characterized in that: described butt junction (8) is for circular, its top has groove (13), the inner chamber lower end is a tapering, with bottom end cover (7) be taper fit, a straight ring section (23) coaxial with instrument manhole appendix (3) arranged between the double tapered.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010206610802U CN201956081U (en) | 2010-12-15 | 2010-12-15 | Shielding transferring device for radioactive substance |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010206610802U CN201956081U (en) | 2010-12-15 | 2010-12-15 | Shielding transferring device for radioactive substance |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN201956081U true CN201956081U (en) | 2011-08-31 |
Family
ID=44500185
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2010206610802U Expired - Lifetime CN201956081U (en) | 2010-12-15 | 2010-12-15 | Shielding transferring device for radioactive substance |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN201956081U (en) |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104282351A (en) * | 2014-09-30 | 2015-01-14 | 南京航空航天大学 | Special dry storage container for spent nuclear fuel |
| CN106345983A (en) * | 2016-08-31 | 2017-01-25 | 上海交通大学 | Lead layer squeeze casting method for depleted fuel storage tank |
| CN106875998A (en) * | 2017-02-23 | 2017-06-20 | 中国核动力研究设计院 | High radioactivity solid waste temporary processing system and method after one kind irradiation |
| CN107161625A (en) * | 2017-06-08 | 2017-09-15 | 中广核研究院有限公司 | Sealed compartment for hazardous materials transportation, the transportation resources using the sealed compartment |
| CN107665745A (en) * | 2017-10-17 | 2018-02-06 | 中国核动力研究设计院 | A kind of high storage container for putting detector assembly |
| CN108597633A (en) * | 2018-04-27 | 2018-09-28 | 清华大学 | The shielding conveyer method and equipment of spentnuclear fuel |
| CN112927856A (en) * | 2021-01-22 | 2021-06-08 | 四川核保锐翔科技有限责任公司 | Nuclear pollution cable recycling shielding barrel device |
-
2010
- 2010-12-15 CN CN2010206610802U patent/CN201956081U/en not_active Expired - Lifetime
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104282351A (en) * | 2014-09-30 | 2015-01-14 | 南京航空航天大学 | Special dry storage container for spent nuclear fuel |
| CN106345983A (en) * | 2016-08-31 | 2017-01-25 | 上海交通大学 | Lead layer squeeze casting method for depleted fuel storage tank |
| CN106345983B (en) * | 2016-08-31 | 2018-05-08 | 上海交通大学 | A kind of lead layer extruding casting hanging method for spentnuclear fuel storage tank |
| CN106875998A (en) * | 2017-02-23 | 2017-06-20 | 中国核动力研究设计院 | High radioactivity solid waste temporary processing system and method after one kind irradiation |
| CN107161625A (en) * | 2017-06-08 | 2017-09-15 | 中广核研究院有限公司 | Sealed compartment for hazardous materials transportation, the transportation resources using the sealed compartment |
| CN107665745A (en) * | 2017-10-17 | 2018-02-06 | 中国核动力研究设计院 | A kind of high storage container for putting detector assembly |
| CN107665745B (en) * | 2017-10-17 | 2019-05-21 | 中国核动力研究设计院 | A kind of high storage container for putting detector assembly |
| CN108597633A (en) * | 2018-04-27 | 2018-09-28 | 清华大学 | The shielding conveyer method and equipment of spentnuclear fuel |
| CN112927856A (en) * | 2021-01-22 | 2021-06-08 | 四川核保锐翔科技有限责任公司 | Nuclear pollution cable recycling shielding barrel device |
| CN112927856B (en) * | 2021-01-22 | 2022-09-13 | 四川核保锐翔科技有限责任公司 | Nuclear pollution cable recycling shielding barrel device |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN201956081U (en) | Shielding transferring device for radioactive substance | |
| CN105355253B (en) | Method for transferring nuclear power station waste filter | |
| CN203839059U (en) | Underwater radioactive waste collection and transfer device | |
| US3179243A (en) | Shielded containers for nuclear fuel elements | |
| CN207765180U (en) | Nuclear power plant's radwaste safe transit cask flask | |
| JP5808812B2 (en) | Equipment for dry transport of nuclear fuel assemblies | |
| SE405903B (en) | DEVICE FOR RECEIVING AND PROTECTING AN ELONG-RADIOACTIVE NUCLEAR FUEL PATTERN | |
| CN1323405C (en) | Straight nuclear reactor fuel assembly refueling, loading and unloading technique | |
| CN107351115B (en) | Irradiation silicon rod grabbing device and method | |
| US4904444A (en) | Method for manipulating and/or storing a nuclear reactor fuel assembly including an elongated skeleton with fuel rods, and a nuclear reactor fuel assembly especially for use with this method | |
| RU2444798C1 (en) | Device for collection of spilt spent nuclear fuel pellets | |
| CN109727697B (en) | High-radioactivity waste receiving device | |
| CN102376375B (en) | Underwater operation device for grabbing end part fitting of nuclear fuel assembly | |
| CN112951466B (en) | Target piece transfer device | |
| CN208256295U (en) | A kind of nuclear power station underwater foreign matter collection transfer device | |
| CN102568633A (en) | Dry-type hoisting method for fuel-lacking assembly | |
| RU77092U1 (en) | DEVICE FOR REMOVING AND TRANSPORTING HEATING ASSEMBLIES | |
| CN102982857A (en) | High-integrity polyethylene container temporary storage warehouse | |
| CN208111102U (en) | A kind of storage container after detector containing high-enriched uranium is retired | |
| RU2154864C1 (en) | Method for removing defective spent fuel assemblies | |
| KR102573873B1 (en) | Apparatus for disposal of In-Core Instrument Assembly | |
| CN214226534U (en) | Filter element replacing and transferring tool for radioactive water filter | |
| RU2739902C1 (en) | Method and device for straightening and covering of deformed by length spent defective control and protection rods | |
| RU2634474C1 (en) | Storage hood cover for spent thermal fuel assemblies of vver-1000 reactor and rod for its removal and placement | |
| CN107644692A (en) | A kind of novel locating device |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term | ||
| CX01 | Expiry of patent term |
Granted publication date: 20110831 |