CN102693770A - Coordinate ground vehicle system of nuclear power plant - Google Patents
Coordinate ground vehicle system of nuclear power plant Download PDFInfo
- Publication number
- CN102693770A CN102693770A CN2012101705462A CN201210170546A CN102693770A CN 102693770 A CN102693770 A CN 102693770A CN 2012101705462 A CN2012101705462 A CN 2012101705462A CN 201210170546 A CN201210170546 A CN 201210170546A CN 102693770 A CN102693770 A CN 102693770A
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- movable fixture
- shielding
- well lid
- radome
- basin
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Abstract
The invention belongs to the technical field of reactor engineering, and particularly discloses a coordinate ground vehicle system of a nuclear power plant, which includes a shielding case, a first movable device and a second movable device, wherein the shielding case is fixed in a hole formed in the first movable device, and a storage basin hoist is arranged in an inner cavity of the shielding case; the first movable device includes a first wheel, the second movable device includes a plurality of beams that are arranged in front-rear way and a second wheel mounted at two ends of the beams, a first track is mounted on the multiple beams, and the first movable device can move left and right along the first track through the first wheel; and a shaft is arranged below the second movable device, a shielding floor is arranged at the top of the shaft, a shaft opening is formed in the shielding floor, a shielding shaft cover is mounted in the shaft opening, and a shaft cover gripping apparatus is arranged above the shielding shaft cover. The coordinate ground vehicle system can realize the precise operation and safe operation of high-temperature reactor spent fuel storage shaft.
Description
Technical field
The invention belongs to the reactor engineering technical field, particularly relate to a kind of nuclear power station coordinate ground truck system.
Background technology
The high temperature nuclear reactor nuclear power station be acknowledged as have the 4th generation the nuclear power principal character nuclear power station, have inherently safe, prevent nuclear proliferation, can produce advantages such as high-temperature technology heat.
Pebble bed high temperature reactor adopts spheric fuel element, and disperse has coated fuel particle in the fuel element.Spheric fuel element is that the fuel particle of some and matrix graphite are fully mixed, and is pressed into the graphite nodule of diameter 50mm, and then the act as a fuel shell of element of the pure graphite of parcel compacting one deck externally, and the fuel element external diameter that suppresses is 60mm.The spherical spentnuclear fuel that pebble bed high temperature reactor is discharged from reactor core needs to adopt suitable hold-up vessel, and is stored in the suitable intermediate storage facility, and wherein feasible a kind of storage scheme is the spentnuclear fuel basin to be put into the shielding storage vertical shaft store.The top of irradiated fuel store vertical shaft is provided with the shielding well lid, and the shielding well lid can be processed by steel, filling lead or concrete, and wherein the cost of concrete shield well lid is minimum.The spentnuclear fuel basin is put into storage vertical shaft or with basin when vertical shaft takes out, at first need shield well lid and mention, carry out the lifting of basin in vertical shaft then and operate.In the operating process of spentnuclear fuel basin and shielding well lid; Needing to overlap through one can pinpoint ground truck system; Basin and well lid suspender are accurately navigated to each storage vertical shaft top; This ground truck system requires under various operating modes, can both guarantee the safe and reliable of basin and well lid hoisting and locating operation.
Also do not have at present a kind ofly can realize the accurate location of high temperature nuclear reactor irradiated fuel store vertical shaft and the equipment of safe operation.
Summary of the invention
The technical matters that (one) will solve
The technical matters that the present invention will solve is: how to realize the accurate location and the safe operation of high temperature nuclear reactor irradiated fuel store vertical shaft.
(2) technical scheme
In order to solve the problems of the technologies described above, the present invention provides a kind of nuclear power station coordinate ground truck system, comprising: radome, first movable fixture and second movable fixture;
Said radome is fixed in the hole of being offered on first movable fixture, and the inner chamber of said radome is provided with the basin suspender;
Said first movable fixture comprises first wheel; Many beams of arranging before and after said second movable fixture comprises and second wheel that is installed in said beam two ends; Be separately installed with first track on the said many beams, said first movable fixture can be through said first wheel along the first track side-to-side movement;
Said second movable fixture below is provided with vertical shaft, and the top of said vertical shaft has well head for the shielding floor on the said shielding floor, the shielding well lid is housed in the said well head, and the said barrier wells side of covering is provided with the well lid gripping apparatus.
Preferably, said vertical shaft is surrounded by side wall.
Preferably, the two ends, cabin of shielding floor top are equipped with second track, and said second movable fixture can seesaw along second track through said second wheel.
Preferably, the bottom of said radome is provided with dismountable base plate.
Preferably; Be fixed with windlass on said first movable fixture, be wound with wire rope on the reel of said windlass, an end of said wire rope is fixed on the said windlass; The other end is fixed on the said basin suspender, leads through the pulley that is arranged on the radome top cover in the middle part.
Preferably, have a plurality of perforates on the said radome top cover, the said perforate of said steel wire penetrating is connected with the basin suspender of radome inner chamber.
Preferably, said system also comprises motor and reductor, and said motor and reductor are fixed on first movable fixture, and the input end of said reductor connects motor, and output terminal connects windlass.
Preferably, said windlass, motor and reductor respectively have two covers.
Preferably, said system also comprises electric block and support, and said electric block is fixed on the support, and is connected with said well lid gripping apparatus through chain, and said support is fixed on said first movable fixture.
Preferably, be fixed with the well lid gib block on the said support.
(3) beneficial effect
Technique scheme has following advantage: can realize the accurate location and the safe operation of high temperature nuclear reactor irradiated fuel store vertical shaft: through the side-to-side movement of first movable fixture and seesawing of second movable fixture, can realize radome and the well lid gripping apparatus accurate location on each well head; On support, be fixed with the well lid gib block,, thereby guaranteed can not rock accurate positioning when barrier wells covers down motion for moving up and down of well lid of shielding provides guiding; Windlass, motor and reductor respectively have two covers, can realize the redundant safety of spentnuclear fuel basin lifting.
Description of drawings
Fig. 1 is the front view of part-structure of the system of the embodiment of the invention;
Fig. 2 is the vertical view of the system of the embodiment of the invention;
Fig. 3 is the sectional view of the embodiment of the invention;
Fig. 4 is the axonometric drawing of the part-structure of the embodiment of the invention.
Wherein, 1 radome; 2 pulleys; 3 wire rope; 4 windlasss; 5 first movable fixtures; 6 first wheels; 7 second movable fixtures; 8 first tracks; 9 second wheels; 10 second tracks; 11 electric blocks; 12 chains; 13 well lid gripping apparatus; 14 well lid gib blocks; 15 supports; 16 reductors; 17 motor; 18 supporting bases; 19 well heads; 20 vertical shafts; 21 side walls; 22 basin suspenders; 23 spentnuclear fuel basins; 24 base plates; 25 shielding floors; 26 shielding well lids.
Embodiment
Below in conjunction with accompanying drawing and embodiment, specific embodiments of the invention describes in further detail.Following examples are used to explain the present invention, but are not used for limiting scope of the present invention.
Like Fig. 1～shown in Figure 4, the structure of the nuclear power station coordinate ground truck system of the embodiment of the invention is following:
The storage vertical shaft 20 of spentnuclear fuel is made up of side wall 21 all around, and the top of vertical shaft 20 is shielding floor 25, has the well head 19 of each vertical shaft 20 on the shielding floor 25, and shielding well lid 26 is housed in the well head 19.
Being separately installed with first track, 8, the first movable fixtures 5 on two beams of second movable fixture 7 can be through installing first wheel, 6 edge first track, 8 side-to-side movements thereunder.The side-to-side movement with first movable fixture 5 of seesawing through second movable fixture 7 can realize radome 1 and the accurate location of well lid gripping apparatus 13 on each well head 19.First movable fixture 5 also comprises car body except comprising first wheel 6, and said car body is processed by steel plate in the present embodiment.
The middle part of first movable fixture 5 has circular hole; Radome 1 is fixed in the circular hole of first movable fixture 5 through supporting base 18; The inner chamber of radome 1 can hold a spentnuclear fuel basin 23; But spentnuclear fuel basin 23 can be placed on the base plate 24 of pull of radome 1 bottom, and base plate 24 can be opened, and spentnuclear fuel basin 23 is hung in and hangs out the inner chamber of radome 1.
The inner chamber of radome 1 is provided with basin suspender 22, is used for lifting spentnuclear fuel basin 23.The windlass 4 that is used to drive 22 risings of basin suspender and descends is fixed on first movable fixture 5; Lay winding wire ropes 3 on the reel of windlass 4; One end of wire rope 3 is fixed on the windlass 4, and an other end is fixed on the basin suspender 22, and is middle through being fixed on pulley 2 guiding on radome 1 top cover; Have a plurality of perforates on radome 1 top cover, wire rope 3 can pass this perforate and be connected with the basin suspender 22 of radome 1 inner chamber.Be used to drive the motor 17 that windlass 4 rotates and also be fixed on first movable fixture 5 with reductor 16, the input end of reductor 16 connects motor 17, and output terminal connects windlass 4.
The windlass 4, motor 17 and the reductor 16 that are used to lift basin suspender 22 respectively have two covers; Can realize the redundant safety of spentnuclear fuel basin 23 liftings; Under the unexpected operating mode that any cover elevator unit fault takes place, still can guarantee the security of spentnuclear fuel basin lifting.
What be used to lift shielding well lid 26 is well lid gripping apparatus 13; Well lid gripping apparatus 13 can grasp shielding well lid 26 or throw off from shielding well lid 26; Be used to drive that well lid gripping apparatus 13 rises and descend is electric block 11; Electric block 11 is fixed on the support 15, and 15 on support is fixed on first movable fixture 5, and electric block 11 is connected on the well lid gripping apparatus 13 through chain 12.Accurate in order to guarantee to shield the direction that well lid 26 moves up and down, support 15 is provided with the well lid gib block 14 of circumference, and well lid gib block 14 is fixed on the support 15, for moving up and down of well lid 26 of shielding provides guiding.
The operating process of this nuclear power station coordinate ground truck system is following:
1, spentnuclear fuel basin 23 is hung in vertical shaft 20 in the radome 1:
Original state is: put into a spentnuclear fuel basin 23 in the radome 1, spentnuclear fuel basin 23 is placed on the pull base plate 24.The well head of each vertical shaft 20 all is equipped with shielding well lid 26.
Operating process is:
Second movable fixture 7 and first movable fixture 5 drive radome 1; Through scrambler or other modes the center of well lid gripping apparatus 13 is accurately navigated in the well head 19 of specifying vertical shaft 20 in the heart; Operation electric block 11 drops to well lid gripping apparatus 13 in the groove of shielding well lid 26; Operation well lid gripping apparatus 13 is caught shielding well lid 26, and operation electric block 11 will shield well lid 26 mentions in well head 19, under the guide effect of well lid gib block 14; Carry to support 15, accomplish the operation that shielding well lid 26 is mentioned in the well head 19.
Second movable fixture 7 is moved in operation, the center of radome 1 is accurately navigated in the well head 19 of specifying vertical shaft 20 in the heart the motor 17 of operation windlass 4 through scrambler or other modes; Basin suspender 22 is mentioned spentnuclear fuel basin 23 from base plate 24, operate then base plate 24 is opened, the motor 17 of operation windlass 4; Basin suspender 22 is transferred spentnuclear fuel basin 23 from the inner chamber of radome 1, through well head 19, spentnuclear fuel basin 23 put to vertical shaft 20 deposit; Operated from a distance basin suspender 22 then; It is thrown off from spentnuclear fuel basin 23, operate the motor 17 of windlass 4, basin suspender 22 is recovered to the inner chamber of radome 1 from vertical shaft 20; Base plate 24 is closed in operation, accomplishes spentnuclear fuel basin 23 and in radome 1, hangs in the operation of storing in the vertical shaft 20.
Second movable fixture 7 is moved in operation; Through scrambler or other modes the center of well lid gripping apparatus 13 is accurately navigated in the well head 19 of specifying vertical shaft 20 in the heart again; Operation electric block 11 will shield well lid 26 with well lid gripping apparatus 13 and transfer to the well head 19 of vertical shaft 20; Operation well lid gripping apparatus 13 makes it throw off from shielding well lid 26, and operation electric block 11 is carried well lid gripping apparatus 13 to support 15 from shielding well lid 26, accomplishes the operation that shielding well lid 26 is returned to well head 19.
2, spentnuclear fuel basin 23 is hung in the radome 1 from vertical shaft 20:
Original state is: do not place spentnuclear fuel basin 23 in the radome 1, base plate 24 is in closed condition.The well head of each vertical shaft 20 all is equipped with shielding well lid 26.
Operating process is:
Second movable fixture 7 and first movable fixture 5 drive radome 1; Through scrambler or other modes the center of well lid gripping apparatus 13 is accurately navigated in the well head 19 of specifying vertical shaft 20 in the heart; Operation electric block 11 drops to well lid gripping apparatus 13 in the groove of shielding well lid 26; Operation well lid gripping apparatus 13 is caught shielding well lid 26, and operation electric block 11 will shield well lid 26 mentions in well head 19, under the guide effect of well lid gib block 14; Carry to support 15, accomplish the operation that shielding well lid 26 is mentioned in the well head 19.
Second movable fixture 7 is moved in operation, through scrambler or other modes the center of radome 1 is accurately navigated in the well head 19 of specifying vertical shaft 20 in the heart, and base plate 24 is opened in operation; The motor 17 of operation windlass 4, basin suspender 22 is transferred from the inner chamber of radome 1, through well head 19; Basin suspender 22 is transferred on the spentnuclear fuel basin of depositing to the vertical shaft 20 23, and operated from a distance basin suspender 22 makes it catch the lifting mouth of spentnuclear fuel basin 23 then; The motor 17 of operation windlass 4; Basin suspender 22 and spentnuclear fuel basin 23 are recovered to the inner chamber of radome 1 from vertical shaft 20, and base plate 24 is closed in operation, operates the motor 17 of windlass 4 then; Spentnuclear fuel basin 23 is transferred on the base plate 24, accomplished spentnuclear fuel basin 23 and hang in the operation that radome 1 inner chamber is deposited from vertical shaft 20.
Second movable fixture 7 is moved in operation; Through scrambler or other modes the center of well lid gripping apparatus 13 is accurately navigated in the well head 19 of specifying vertical shaft 20 in the heart again; Operation electric block 11 will shield well lid 26 with well lid gripping apparatus 13 and transfer to the well head 19 of vertical shaft 20; Operation well lid gripping apparatus 13 makes it throw off from shielding well lid 26, and operation electric block 11 is carried well lid gripping apparatus 13 to support 15 from shielding well lid 26, accomplishes the operation that shielding well lid 26 is returned to well head 19.
Can find out that by above embodiment the nuclear power station coordinate ground truck system that the embodiment of the invention proposes has the following advantages:
1. can realize the long-distance remote control operation of second movable fixture 7 and first movable fixture 5, avoid operating personnel closely to operate and receive radiation;
2. through the mode of scrambler second movable fixture 7 and first movable fixture 5 are accurately located, can improve the reliability of operations;
3. through radome the spentnuclear fuel basin is carried out radiation shield, can allow closely operation and maintenance of operating personnel, avoid receiving radiation;
4. the windlass that is used to lift basin has two covers, can realize the redundant safety of spentnuclear fuel basin lifting, under the unexpected operating mode that any cover elevator unit fault takes place, still can guarantee the security of spentnuclear fuel basin lifting;
5. can realize shielding the long-distance remote control operation of well lid lifting, avoid operating personnel closely to operate and receive radiation;
6. can realize the long-distance remote control operation of basin lifting, avoid operating personnel closely to operate and receive radiation;
7. through the integrated design of equipment such as car, radome, well lid suspender, basin suspender over the ground, can realize each item function of spentnuclear fuel basin storage operation, satisfy the integrated requirement of nuclear power station.
System of the present invention can realize the accurate location and the safe operation of high temperature nuclear reactor irradiated fuel store vertical shaft; This ground truck system is through suitably revising; Can be used to operate spentnuclear fuel basin, shielding well lid or other equipment in pressurized-water reactor nuclear power plant and other types of nuclear power station, also can be applicable to accurate location and lifting operation under all kinds of operating modes of general industry.
The above only is a preferred implementation of the present invention; Should be pointed out that for those skilled in the art, under the prerequisite that does not break away from know-why of the present invention; Can also make some improvement and replacement, these improvement and replacement also should be regarded as protection scope of the present invention.
Claims (10)
1. a nuclear power station coordinate ground truck system is characterized in that, comprising: radome (1), first movable fixture (5) and second movable fixture (7);
Said radome (1) is fixed in the hole of being offered on first movable fixture (5), and the inner chamber of said radome (1) is provided with basin suspender (22);
Said first movable fixture (5) comprises first wheel (6); Many beams of arranging before and after said second movable fixture (7) comprises and second wheel (9) that is installed in said beam two ends; Be separately installed with first track (8) on the said many beams, said first movable fixture (5) can be through said first wheel (6) along first track (8) side-to-side movement;
Said second movable fixture (7) below is provided with vertical shaft (20); The top of said vertical shaft (20) is shielding floor (25); Have well head (19) on the said shielding floor (25), shielding well lid (26) is housed in the said well head (19), said shielding well lid (26) top is provided with well lid gripping apparatus (13).
2. the system of claim 1 is characterized in that, said vertical shaft (20) is surrounded by side wall (21).
3. the system of claim 1 is characterized in that, the two ends, cabin of shielding floor (25) top are equipped with second track (10), and said second movable fixture (7) can seesaw along second track (10) through said second wheel (9).
4. the system of claim 1 is characterized in that, the bottom of said radome (1) is provided with dismountable base plate (24).
5. the system of claim 1; It is characterized in that; Be fixed with windlass (4) on said first movable fixture (5), be wound with wire rope (3) on the reel of said windlass (4), an end of said wire rope (3) is fixed on the said windlass (4); The other end is fixed on the said basin suspender (22), leads through the pulley (2) that is arranged on radome (1) top cover in the middle part.
6. system as claimed in claim 5 is characterized in that, has a plurality of perforates on said radome (1) top cover, and said wire rope (3) passes said perforate and is connected with the basin suspender (22) of radome (1) inner chamber.
7. system as claimed in claim 5; It is characterized in that; Said system also comprises motor (17) and reductor (16); Said motor (17) and reductor (16) are fixed on first movable fixture (5), and the input end of said reductor (16) connects motor (17), and output terminal connects windlass (4).
8. system as claimed in claim 7 is characterized in that, said windlass (4), motor (17) and reductor (16) respectively have two covers.
9. like each described system in the claim 1～8; It is characterized in that; Said system also comprises electric block (11) and support (15); Said electric block (11) is fixed on the support (15), and is connected with said well lid gripping apparatus (13) through chain (12), and said support (15) is fixed on said first movable fixture (5).
10. system as claimed in claim 9 is characterized in that, is fixed with well lid gib block (14) on the said support (15).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012101705462A CN102693770A (en) | 2012-05-28 | 2012-05-28 | Coordinate ground vehicle system of nuclear power plant |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012101705462A CN102693770A (en) | 2012-05-28 | 2012-05-28 | Coordinate ground vehicle system of nuclear power plant |
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| CN102693770A true CN102693770A (en) | 2012-09-26 |
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| CN2012101705462A Pending CN102693770A (en) | 2012-05-28 | 2012-05-28 | Coordinate ground vehicle system of nuclear power plant |
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN104485144A (en) * | 2014-12-08 | 2015-04-01 | 中广核工程有限公司 | Shielding device for transferring radioactive waste bins of nuclear power plants |
| CN107837465A (en) * | 2017-11-21 | 2018-03-27 | 西安大医数码科技有限公司 | One kind stem apparatus and system |
| WO2018191852A1 (en) * | 2017-04-17 | 2018-10-25 | 西安大医数码技术有限公司 | Source removing and introducing tooling, smart cart and source removing and introducing system |
| CN110415856A (en) * | 2019-07-09 | 2019-11-05 | 江苏中海华核环保有限公司 | It is a kind of to detect bucket cake surface radiological dose automatically and carry out the preferred compacting machine of barrel cake |
| CN110544546A (en) * | 2018-07-18 | 2019-12-06 | 中国核电工程有限公司 | transfer system for storage |
| CN110642176A (en) * | 2019-10-22 | 2020-01-03 | 浙江工业大学 | Inspection shaft lid transport mechanism |
| CN112408207A (en) * | 2020-11-06 | 2021-02-26 | 莱德沃重工机械(上海)有限公司 | Loader, system and method for storing and taking radiation articles |
| CN112820430A (en) * | 2019-11-18 | 2021-05-18 | 中国核工业二三建设有限公司 | Method for installing and constructing high-temperature gas cooled reactor graphite and carbon reactor internal member and installing trolley |
| CN112951467A (en) * | 2021-01-29 | 2021-06-11 | 中国原子能科学研究院 | Filter core transfer device |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN2238182Y (en) * | 1995-05-29 | 1996-10-23 | 武汉列电实业公司 | Tripper for vehicle |
| JP3917998B2 (en) * | 2004-11-08 | 2007-05-23 | 三菱重工業株式会社 | Storage system, and storage container and container transport device used for storage system |
| CN201183713Y (en) * | 2008-04-03 | 2009-01-21 | 中国有色（沈阳）冶金机械有限公司 | Lifting guide means for blanking tube of aluminum electrolysis multifunctional crane |
| CN101740147A (en) * | 2009-12-17 | 2010-06-16 | 清华大学 | Dry vertical shaft storage system for spent fuel of nuclear power station and storage method thereof |
| CN201534754U (en) * | 2009-06-03 | 2010-07-28 | 张智坤 | Numerical control crane used in radioactive storage depot |
| CN101916605A (en) * | 2010-07-26 | 2010-12-15 | 清华大学 | Complete device of spent fuel storage tank and shielding cover of nuclear power plant |
| CN102182834A (en) * | 2011-05-05 | 2011-09-14 | 清华大学 | Ventilation control single-blade butterfly valve for high temperature reactor nuclear power plant |
-
2012
- 2012-05-28 CN CN2012101705462A patent/CN102693770A/en active Pending
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN2238182Y (en) * | 1995-05-29 | 1996-10-23 | 武汉列电实业公司 | Tripper for vehicle |
| JP3917998B2 (en) * | 2004-11-08 | 2007-05-23 | 三菱重工業株式会社 | Storage system, and storage container and container transport device used for storage system |
| CN201183713Y (en) * | 2008-04-03 | 2009-01-21 | 中国有色（沈阳）冶金机械有限公司 | Lifting guide means for blanking tube of aluminum electrolysis multifunctional crane |
| CN201534754U (en) * | 2009-06-03 | 2010-07-28 | 张智坤 | Numerical control crane used in radioactive storage depot |
| CN101740147A (en) * | 2009-12-17 | 2010-06-16 | 清华大学 | Dry vertical shaft storage system for spent fuel of nuclear power station and storage method thereof |
| CN101916605A (en) * | 2010-07-26 | 2010-12-15 | 清华大学 | Complete device of spent fuel storage tank and shielding cover of nuclear power plant |
| CN102182834A (en) * | 2011-05-05 | 2011-09-14 | 清华大学 | Ventilation control single-blade butterfly valve for high temperature reactor nuclear power plant |
Cited By (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104485144A (en) * | 2014-12-08 | 2015-04-01 | 中广核工程有限公司 | Shielding device for transferring radioactive waste bins of nuclear power plants |
| US11133116B2 (en) | 2017-04-17 | 2021-09-28 | Our United Corporation | Radioactive source removing and introducing tooling, smart cart and source removing and introducing system |
| WO2018191852A1 (en) * | 2017-04-17 | 2018-10-25 | 西安大医数码技术有限公司 | Source removing and introducing tooling, smart cart and source removing and introducing system |
| CN110326057A (en) * | 2017-04-17 | 2019-10-11 | 西安大医集团有限公司 | A kind of pick-and-place source tooling, intelligent carriage and pick-and-place source system |
| CN110326057B (en) * | 2017-04-17 | 2023-09-15 | 西安大医集团股份有限公司 | Get and put source frock, intelligent dolly and get and put source system |
| CN107837465A (en) * | 2017-11-21 | 2018-03-27 | 西安大医数码科技有限公司 | One kind stem apparatus and system |
| CN107837465B (en) * | 2017-11-21 | 2024-05-14 | 西安大医集团股份有限公司 | Source guiding device and system |
| CN110544546A (en) * | 2018-07-18 | 2019-12-06 | 中国核电工程有限公司 | transfer system for storage |
| CN110415856A (en) * | 2019-07-09 | 2019-11-05 | 江苏中海华核环保有限公司 | It is a kind of to detect bucket cake surface radiological dose automatically and carry out the preferred compacting machine of barrel cake |
| CN110415856B (en) * | 2019-07-09 | 2020-07-10 | 江苏中海华核环保有限公司 | Compactor capable of automatically detecting surface radiation dose of drum cake and performing drum cake optimization |
| CN110642176A (en) * | 2019-10-22 | 2020-01-03 | 浙江工业大学 | Inspection shaft lid transport mechanism |
| CN112820430A (en) * | 2019-11-18 | 2021-05-18 | 中国核工业二三建设有限公司 | Method for installing and constructing high-temperature gas cooled reactor graphite and carbon reactor internal member and installing trolley |
| CN112820430B (en) * | 2019-11-18 | 2024-05-14 | 中国核工业二三建设有限公司 | Method for installing and building graphite and carbon internal components of high-temperature gas cooled reactor and installation trolley |
| CN112408207A (en) * | 2020-11-06 | 2021-02-26 | 莱德沃重工机械(上海)有限公司 | Loader, system and method for storing and taking radiation articles |
| CN112951467A (en) * | 2021-01-29 | 2021-06-11 | 中国原子能科学研究院 | Filter core transfer device |
| CN112951467B (en) * | 2021-01-29 | 2024-03-22 | 中国原子能科学研究院 | Filter core transfer device |
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Application publication date: 20120926 |