CN109979626A - A kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system and method - Google Patents
A kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system and method Download PDFInfo
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- CN109979626A CN109979626A CN201711441544.1A CN201711441544A CN109979626A CN 109979626 A CN109979626 A CN 109979626A CN 201711441544 A CN201711441544 A CN 201711441544A CN 109979626 A CN109979626 A CN 109979626A
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- 238000000034 method Methods 0.000 title claims abstract description 43
- 230000009182 swimming Effects 0.000 title claims abstract description 26
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 25
- 239000000446 fuel Substances 0.000 claims abstract description 112
- 239000002915 spent fuel radioactive waste Substances 0.000 claims abstract description 28
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 16
- 238000003860 storage Methods 0.000 claims abstract description 15
- 238000007689 inspection Methods 0.000 claims abstract description 9
- 230000033001 locomotion Effects 0.000 claims description 22
- 238000012790 confirmation Methods 0.000 claims description 9
- 210000000078 claw Anatomy 0.000 claims description 6
- 230000007423 decrease Effects 0.000 claims description 6
- 230000001737 promoting effect Effects 0.000 claims description 3
- 239000007787 solid Substances 0.000 claims 1
- 238000010438 heat treatment Methods 0.000 abstract description 4
- 238000010586 diagram Methods 0.000 description 3
- 229910000831 Steel Inorganic materials 0.000 description 2
- 230000005540 biological transmission Effects 0.000 description 2
- 230000014759 maintenance of location Effects 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000002955 isolation Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Manipulator (AREA)
Abstract
The present invention relates to swimming pool type heating reactor fuel handling technical fields, specifically disclose a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system and method.Fuel manipulator crane can arbitrarily move between connected reactor core pond and Spent Fuel Pool in the system；For underwater auxiliary loading and unloading stage+module above the reactor core pond on inspection platform, fuel manipulator crane can carry out the charge and discharge operations of fuel in reactor core pool area by auxiliary fuel manipulator crane.The fuel assembly of reactor core any position can be accurately grabbed, and can be by its complete envelope in fixes sleeve, and be transported to irradiated fuel assembly storage screen work；The system and method ensures that personnel during loading and unloading, fuel assembly, equipment safety are controllable and technical feasibility；Opposite pressurized-water reactor nuclear power plant fuel handling and bunkerage, under the premise of meeting the function and performance requirement of deep water refueling operation, all relevant devices that reload of the invention are simpler, it is higher that technical maturity can be achieved and have stronger cost advantage.
Description
Technical field
The invention belongs to pool type heating reactor fuel handling technical fields of swimming, and in particular to a kind of swimming pool formula atmospheric low-temperature heat supply
Heap fuel handling system and method.
Background technique
Swimming pool formula low temperature heating reactor (hereinafter referred to as " low temperature heap ") is the specific requirement for nuclear heating, with swimmer's pool
The innovative technology of process heat reactor reasonably reduces the operating temperature of reactor, heat reactor is allow to work in normal pressure swimmer's pool
It is interior, so that reactor system and equipment is carried out the simplification of essence compared with pressurized reactor.From the angle of fuel handling, with pressure water
Heap is compared different more particularly to the following aspects:
1, low temperature heap reactor core and Spent Fuel Pool share the same workshop, and the two is realized by unlatching/closing of sluice gate
Connection and isolation realize component in the transhipment of reactor core and weary pond；Pressurized-water reactor nuclear power plant reactor core reactor building is with fuel plant
Separation, irradiated fuel assembly from reactor core draw off after in refuelling pool by fuel transmission channel realization fuel assembly in reactor core and weary
Transhipment between fuel pit；
2, pressurized water reactor core upper pipe seat of fuel component is apart from about 12.5 meters of fuel manipulator crane track, low temperature heap reactor fuel component
Upper tube seat spacing is higher for the crawl positioning requirements of fuel from about 21 meters of fuel manipulator crane track；
3, since low temperature heap does not have fuel transmission channel, it is therefore necessary to have special fuel handler to carry out fuel
Transhipment.
Summary of the invention
It, can be with the purpose of the present invention is to provide a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system and method
It realizes reactor reloading pattern and the out processes such as irradiated fuel assembly transport, storage after heap, achievees the purpose that safe, feasible, economical.
Technical scheme is as follows: a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system, the system include
Fuel manipulator crane and underwater auxiliary loading and unloading platform, wherein fuel manipulator crane can connected reactor core pond and Spent Fuel Pool it
Between arbitrarily move；For underwater auxiliary loading and unloading stage+module above the reactor core pond on inspection platform, fuel manipulator crane can pass through auxiliary
Fuel manipulator crane carries out the charge and discharge operations of fuel in reactor core pool area.
The fuel manipulator crane includes bridge orbit, cart, trolley, fixes sleeve and extension sleeve, wherein gantry rail
Road is laid on the top of Spent Fuel Pool and reactor core pond；The cart can be carried out along the bridge orbit in X-direction
Movement；Track is equipped in the horizontal Y-direction vertical with X-direction on cart, and is equipped with trolley on that track, below trolley
It is fixedly installed with grabbing assembly, and the control grabbing assembly of the main electromotor structure by being mounted on trolley is realized to fuel assembly
Crawl.
The grabbing assembly includes fixes sleeve, extension sleeve and pawl tool, wherein the fixed peace of the fixes sleeve
Mounted in the lower end of trolley, the extension sleeve upper end in fixes sleeve is connected with main electromotor structure, and in extension sleeve
Lower end has equipped with pawl.
It is additionally provided with auxiliary lifting mechanism on the cart, the auxiliary emergency set as main electromotor structure.
The underwater auxiliary loading and unloading platform includes leading arm and platform base, wherein platform base is mounted on maintenance
On platform, guide rail is installed on platform base, a pair of of leading arm is mounted on the guide rail of platform base, and can pass through leading arm
The accurate positioning to fuel assembly below inspection platform is realized in movement on platform base guide rail.
The leading arm is the box typed structure with " zigzag " pilot hole, and is equipped with driving mechanism inside it,
Close up to form rectangular guiding hole array by two leading arms, realizes accurate, the reliable guide-localization to extension sleeve.
The fixes sleeve lower end surface is higher than the sluice gate being arranged between Spent Fuel Pool and reactor core pond.
A kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling method, this method specifically comprise the following steps:
Step 1, state and coordinate according to desired fuel component, adjust the position of fuel manipulator crane, and grab fuel assembly；
Step 2 promotes grabbed fuel assembly using fuel manipulator crane；
Step 3 shifts fuel assembly and is stored in Spent Fuel Pool screen work.
The step 1 specifically includes:
Step 1.1, state and coordinate according to desired fuel component move cart and trolley in fuel manipulator crane, make to stretch
The pawl tool of contracting barrel end is located at right above reactor core crawl target position；
Step 1.2, using low speed, high speed, low speed motion mode, extension sleeve 16 is lowered into underwater auxiliary loading and unloading
In platform at the position of leading arm；
Step 1.3 is automatically positioned using leading arm, and the auxiliary guiding of the pairs of extension sleeve main frame of closed；
Step 1.4, using low speed, high speed, low speed motion mode, by extension sleeve drop to pawl tool to fuel assembly
Pre- crawl position；
Step 1.5 grabs fuel assembly.
The step 2 specifically includes:
Step 2.1 has the act bit for assisting leading arm in loading and unloading platform under water by promoting extension sleeve to pawl；
Step 2.2, leading arm separate and restore initial position；
Step 2.3, with low speed, high speed, low speed motion mode, fuel assembly is promoted to fixing sleeve using extension sleeve
In cylinder.
The step 3 specifically includes:
Step 3.1, according to stored target location status and coordinate, using cart and trolley, fixes sleeve is passed through into sluice
Behind the door, it is moved to right above Spent Fuel Pool screen work stored target position；
Step 3.2, with low speed, high speed, low speed motion mode, decline extension sleeve, and confirm that fuel assembly whether can
In enough smoothly storages to Spent Fuel Pool storage screen work；
Step 3.3, low speed decline extension sleeve, drop to fuel assembly on Spent Fuel Pool storage screen work bottom, steel
When cord load sensing device reaches threshold value, stop descending motion；
Step 3.4, driving claw tool separate with upper pipe seat of fuel component, and check confirmation.
Step 3.5, in a manner of low speed, high speed, low speed, extension sleeve is promoted in fixes sleeve, complete fuel stack
It is grabbed in part reactor core pond and the storage in Spent Fuel Pool screen work.
The specific steps that fuel assembly is grabbed in the step 1.5 are as follows:
Step 1.5.1, confirmation pawl tool and upper pipe seat of fuel component relative positional relationship；
Step 1.5.2, low speed declines extension sleeve and is located in upper pipe seat of fuel component to it, wire rope load inductor
Stop descending motion when reaching threshold value；
Step 1.5.3, driving claw tool declines and engages with upper pipe seat of fuel component, and checks confirmation.
Remarkable result of the invention is: a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system of the present invention
And method, the fuel assembly of reactor core any position can be accurately grabbed, and can be by its complete envelope in fixes sleeve, and be transported to
Irradiated fuel assembly stores screen work；The system and method ensures that personnel during loading and unloading, fuel assembly, equipment safety are controllable and skill
Art is feasible；Opposite pressurized-water reactor nuclear power plant fuel handling and bunkerage, in the function and performance requirement for meeting deep water refueling operation
Under the premise of, all relevant devices that reload of the invention are simpler, it is higher that technical maturity can be achieved and it is excellent to have stronger cost
Gesture.
Detailed description of the invention
Fig. 1 is a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system structural schematic diagram of the present invention；
Fig. 2 is the structural schematic diagram of fuel manipulator crane in Fig. 1；
Fig. 3 is the structural schematic diagram for assisting loading and unloading platform in Fig. 1 under water；
In figure: 1, fuel manipulator crane；2, loading and unloading platform is assisted under water；3, inspection platform；4, fuel assembly；5, reactor core water
Pond；6, spent fuel storage rack；7, Spent Fuel Pool；8, sluice gate；9, auxiliary lifting mechanism；10, main electromotor structure；11, it controls
Cabinet processed；12, bridge orbit；13, trolley；14, cart；15, fixes sleeve；16, extension sleeve；17, gripping apparatus.
Specific embodiment
The present invention will be further described in detail below with reference to the accompanying drawings and specific embodiments.
As shown in Figures 1 to 3, a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system, including fuel manipulator crane 1 and water
Lower auxiliary loading and unloading platform 2, wherein fuel manipulator crane 1 can arbitrarily move between Spent Fuel Pool 7 and connected reactor core pond 5
It is dynamic, it is underwater that loading and unloading platform 2 is assisted to be mounted on 5 top inspection platform 3 of reactor core pond, by assisting loading and unloading platform 2 under water
Fuel manipulator crane 1 can be assisted to carry out the charge and discharge operations of fuel in 5 region of reactor core pond；Fuel manipulator crane 1 includes bridge orbit 12, cart
14, trolley 13, fixes sleeve 15 and extension sleeve 16, wherein bridge orbit 12 is laid on Spent Fuel Pool 7 and reactor core water
The top in pond 5, and cart 14 is equipped in the bridge orbit 12, make cart 14 can along bridge orbit 12 in Spent Fuel Pool 7 and
X-direction is run between reactor core pond 5, auxiliary lifting mechanism 9 is equipped on cart 14, the auxiliary as main electromotor structure 10 is answered
Anxious equipment；Track is installed in the Y-direction of vertical 14 traveling X-direction of cart on cart 14, and is equipped on that track small
Vehicle 13 move trolley can independently along the X direction；Fixes sleeve 15 is installed below trolley 13, and in fixes sleeve
Extension sleeve 16 is cased in 15, main electromotor structure 10 is mounted on trolley 13, and is connected with the upper end of extension sleeve 16, and lead to
It crosses the control cabinet 11 installed on trolley 13 and controls extension sleeve 16 along the movement of vertical Z-direction；Pacify in the end of extension sleeve 16
Equipped with pawl tool 17, it can be used for grabbing fuel assembly 4；15 bottom of fixes sleeve is higher than sluice gate 8, in 17 crawl fuel stack of pawl tool
After part 4, under the action of main electromotor structure 10, fuel assembly 4 follows extension sleeve 16 to rise together, finally can be by fuel assembly
4 are promoted to completely in fixes sleeve 15, to guarantee that whole device passes through sluice gate 8；Underwater auxiliary loading and unloading platform 2 wraps
Include leading arm 19 and platform base 18, wherein platform base 18 is mounted on inspection platform 3, and in 18 bottom four of platform base
Respectively there is one group of adjustment mechanism in week, can be adjusted in a certain range along X, Y and Z-direction；Leading arm 19 is fixed on platform base
It on the guide rail of seat 18, move two leading arms 19 can on 18 guide rail of platform base, wherein leading arm 19 is with " sawtooth
The box typed structure of shape " pilot hole, and inside it include driving mechanism, when extension sleeve is gone up and down to working platform absolute altitude position
When, leading arm 19 to form rectangular guiding hole array and carry out accurate, reliable guide-localization to extension sleeve 16 by closing up；Utilize two
The accurate positioning to all position fuel assemblies 4 of reactor core is realized in the adjustment of a 19 position of leading arm.
A kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling method, this method specifically comprise the following steps:
Step 1, state and coordinate according to desired fuel component, adjust the position of fuel manipulator crane, and grab fuel assembly；
Step 1.1, state and coordinate according to desired fuel component move cart and trolley in fuel manipulator crane, make to stretch
The pawl tool of contracting barrel end is located at right above reactor core crawl target position；
Step 1.2, using low speed, high speed, low speed motion mode, extension sleeve 16 is lowered into underwater auxiliary loading and unloading
In platform at the position of leading arm；
Step 1.3 is automatically positioned using leading arm, and the auxiliary guiding of the pairs of extension sleeve main frame of closed；
Step 1.4, using low speed, high speed, low speed motion mode, by extension sleeve drop to pawl tool to fuel assembly
Pre- crawl position；
Step 1.5 grabs fuel assembly；
Step 1.5.1, confirmation pawl tool and upper pipe seat of fuel component relative positional relationship；
Step 1.5.2, low speed declines extension sleeve and is located in upper pipe seat of fuel component to it, wire rope load inductor
Stop descending motion when reaching threshold value；
Step 1.5.3, driving claw tool declines and engages with upper pipe seat of fuel component, and checks confirmation；
Step 2 promotes grabbed fuel assembly using fuel manipulator crane；
Step 2.1 has the act bit for assisting leading arm in loading and unloading platform under water by promoting extension sleeve to pawl；
Step 2.2, leading arm separate and restore initial position；
Step 2.3, with low speed, high speed, low speed motion mode, fuel assembly is promoted to fixing sleeve using extension sleeve
In cylinder；
Step 3 shifts fuel assembly and is stored in Spent Fuel Pool screen work；
Step 3.1, according to stored target location status and coordinate, using cart and trolley, fixes sleeve is passed through into sluice
Behind the door, it is moved to right above Spent Fuel Pool screen work stored target position；
Step 3.2, with low speed, high speed, low speed motion mode, decline extension sleeve, and confirm that fuel assembly whether can
In enough smoothly storages to Spent Fuel Pool storage screen work；
Step 3.3, low speed decline extension sleeve, drop to fuel assembly on Spent Fuel Pool storage screen work bottom, steel
When cord load sensing device reaches threshold value, stop descending motion；
Step 3.4, driving claw tool separate with upper pipe seat of fuel component, and check confirmation.
Step 3.5, in a manner of low speed, high speed, low speed, extension sleeve is promoted in fixes sleeve, complete fuel stack
It is grabbed in part reactor core pond and the storage in Spent Fuel Pool screen work.
Claims (12)
1. a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system, it is characterised in that: the system include fuel manipulator crane (1) with
And underwater auxiliary loading and unloading platform (2), wherein fuel manipulator crane (1) can be in connected reactor core pond (5) and Spent Fuel Pool (7)
Between arbitrarily move；Underwater auxiliary loading and unloading platform (2) is mounted on above reactor core pond (5) on inspection platform (3), fuel manipulator crane
(1) charge and discharge operations of fuel can be carried out in reactor core pond (5) region by auxiliary fuel manipulator crane (1).
2. a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system according to claim 1, it is characterised in that: described
Fuel manipulator crane (1) include bridge orbit (12), cart (14), trolley (13), fixes sleeve (15) and extension sleeve (16),
Wherein, bridge orbit (12) is laid on the top of Spent Fuel Pool (7) and reactor core pond (5)；The cart (14) can edge
The bridge orbit (12) is moved in X-direction；Rail is equipped in the horizontal Y-direction vertical with X-direction on cart (14)
Road, and trolley (13) are equipped on that track, it is fixedly installed with grabbing assembly below trolley (13), and by being mounted on trolley
(13) main electromotor structure (10) the control grabbing assembly on realizes the crawl to fuel assembly.
3. a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system according to claim 2, it is characterised in that: described
Grabbing assembly include fixes sleeve (15), extension sleeve (16) and pawl tool (17), wherein the fixes sleeve (15) is solid
Dingan County is mounted in the lower end of trolley (13), is located at extension sleeve (16) upper end in fixes sleeve (15) and main electromotor structure (10) phase
Connection, and pawl tool (17) is equipped in the lower end of extension sleeve (16).
4. a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system according to claim 2, it is characterised in that: described
Cart (14) on be additionally provided with auxiliary lifting mechanism (9), the auxiliary emergency set as main electromotor structure (10).
5. a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system according to claim 1, it is characterised in that: described
Underwater auxiliary loading and unloading platform (2) include leading arm (19) and platform base (18), wherein platform base (18) is mounted on inspection
On equating platform (3), guide rail is installed on platform base (18), a pair of of leading arm (19) is mounted on the guide rail of platform base (18)
On, and can be realized by movement of the leading arm (19) on platform base (18) guide rail to fuel assembly below inspection platform (3)
(4) accurate positioning.
6. a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system according to claim 5, it is characterised in that: described
Leading arm (19) be the box typed structure with " zigzag " pilot hole, and inside it be equipped with driving mechanism, pass through two
Leading arm (19) closes up to form rectangular guiding hole array, realizes accurate, the reliable guide-localization to extension sleeve (16).
7. a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system according to claim 3, it is characterised in that: described
Fixes sleeve (16) lower end surface be higher than the sluice gate (8) that is arranged between Spent Fuel Pool (7) and reactor core pond (5).
8. a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling method, it is characterised in that: this method specifically comprises the following steps:
Step 1, state and coordinate according to desired fuel component, adjust the position of fuel manipulator crane, and grab fuel assembly；
Step 2 promotes grabbed fuel assembly using fuel manipulator crane；
Step 3 shifts fuel assembly and is stored in Spent Fuel Pool screen work.
9. a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling method according to claim 8, it is characterised in that: described
Step 1 specifically include:
Step 1.1, state and coordinate according to desired fuel component move cart and trolley in fuel manipulator crane, make telescopic
The pawl tool of cylinder end is located at right above reactor core crawl target position；
Step 1.2, using low speed, high speed, low speed motion mode, extension sleeve 16 is lowered into underwater auxiliary loading and unloading platform
At the position of middle leading arm；
Step 1.3 is automatically positioned using leading arm, and the auxiliary guiding of the pairs of extension sleeve main frame of closed；
Step 1.4, using low speed, high speed, low speed motion mode, by extension sleeve drop to pawl tool the pre- of fuel assembly is grabbed
Fetch bit is set；
Step 1.5 grabs fuel assembly.
10. a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling method according to claim 8, it is characterised in that: institute
The step 2 stated specifically includes:
Step 2.1 has the act bit for assisting leading arm in loading and unloading platform under water by promoting extension sleeve to pawl；
Step 2.2, leading arm separate and restore initial position；
Step 2.3, with low speed, high speed, low speed motion mode, fuel assembly is promoted to fixes sleeve using extension sleeve
It is interior.
11. a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling method according to claim 8, it is characterised in that: institute
The step 3 stated specifically includes:
Step 3.1, according to stored target location status and coordinate, using cart and trolley, by fixes sleeve after sluice gate,
It is moved to right above Spent Fuel Pool screen work stored target position；
Step 3.2, with low speed, high speed, low speed motion mode, decline extension sleeve, and confirm whether fuel assembly can be suitable
In benefit storage to Spent Fuel Pool storage screen work；
Step 3.3, low speed decline extension sleeve, drop to fuel assembly on Spent Fuel Pool storage screen work bottom, wirerope
When load sensing device reaches threshold value, stop descending motion；
Step 3.4, driving claw tool separate with upper pipe seat of fuel component, and check confirmation.
Step 3.5, in a manner of low speed, high speed, low speed, extension sleeve is promoted in fixes sleeve, complete fuel assembly core
It is grabbed in core pond and the storage in Spent Fuel Pool screen work.
12. a kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling method according to claim 9, it is characterised in that: institute
The specific steps that fuel assembly is grabbed in the step 1.5 stated are as follows:
Step 1.5.1, confirmation pawl tool and upper pipe seat of fuel component relative positional relationship；
Step 1.5.2, low speed declines extension sleeve and is located in upper pipe seat of fuel component to it, and wire rope load inductor reaches
Stop descending motion when threshold value；
Step 1.5.3, driving claw tool declines and engages with upper pipe seat of fuel component, and checks confirmation.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201711441544.1A CN109979626B (en) | 2017-12-27 | 2017-12-27 | Swimming pool type normal pressure low temperature heat supply stack fuel loading and unloading system and method |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201711441544.1A CN109979626B (en) | 2017-12-27 | 2017-12-27 | Swimming pool type normal pressure low temperature heat supply stack fuel loading and unloading system and method |
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| CN109979626B CN109979626B (en) | 2024-04-09 |
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| CN114582537A (en) * | 2020-11-30 | 2022-06-03 | 中国核工业二三建设有限公司 | Automatic moving system of spent fuel storage grillwork for nuclear island fuel plant |
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| CN110736427A (en) * | 2019-10-25 | 2020-01-31 | 中国核动力研究设计院 | Machine vision positioning system and positioning method for reactor detector assembly dismantling device |
| CN110736427B (en) * | 2019-10-25 | 2021-05-18 | 中国核动力研究设计院 | Machine vision positioning system and positioning method for reactor detector assembly dismantling device |
| CN111028968A (en) * | 2019-12-31 | 2020-04-17 | 中国科学院合肥物质科学研究院 | Loading and unloading system for reactor and method thereof |
| CN114582537A (en) * | 2020-11-30 | 2022-06-03 | 中国核工业二三建设有限公司 | Automatic moving system of spent fuel storage grillwork for nuclear island fuel plant |
| CN114582537B (en) * | 2020-11-30 | 2023-07-14 | 中国核工业二三建设有限公司 | Spent fuel storage grillwork automatic moving system for nuclear island fuel plant |
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| CN109979626B (en) | 2024-04-09 |
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