CN109979626B - Swimming pool type normal pressure low temperature heat supply stack fuel loading and unloading system and method - Google Patents
Swimming pool type normal pressure low temperature heat supply stack fuel loading and unloading system and method Download PDFInfo
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- CN109979626B CN109979626B CN201711441544.1A CN201711441544A CN109979626B CN 109979626 B CN109979626 B CN 109979626B CN 201711441544 A CN201711441544 A CN 201711441544A CN 109979626 B CN109979626 B CN 109979626B
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- 239000000446 fuel Substances 0.000 title claims abstract description 99
- 238000000034 method Methods 0.000 title claims abstract description 21
- 230000009182 swimming Effects 0.000 title claims abstract description 14
- 239000002915 spent fuel radioactive waste Substances 0.000 claims abstract description 34
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 13
- 230000000712 assembly Effects 0.000 claims abstract description 7
- 238000000429 assembly Methods 0.000 claims abstract description 7
- 210000000078 claw Anatomy 0.000 claims description 22
- 230000007246 mechanism Effects 0.000 claims description 18
- 238000010438 heat treatment Methods 0.000 claims description 10
- 229910000831 Steel Inorganic materials 0.000 claims description 6
- 239000010959 steel Substances 0.000 claims description 6
- 238000003491 array Methods 0.000 claims description 2
- 238000012790 confirmation Methods 0.000 claims description 2
- 238000005516 engineering process Methods 0.000 abstract description 3
- 238000012423 maintenance Methods 0.000 description 4
- 239000003758 nuclear fuel Substances 0.000 description 4
- 230000005540 biological transmission Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000001363 water suppression through gradient tailored excitation 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
-
- 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)
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Abstract
The invention relates to the technical field of swimming pool type heat supply stack fuel operation, and particularly discloses a swimming pool type normal pressure low temperature heat supply stack fuel loading and unloading system and method. The loading and unloading machine of the system can move freely between the connected reactor core water tank and the spent fuel water tank; the underwater auxiliary loading and unloading platform is arranged on the overhaul platform above the reactor core pool, and the loading and unloading machine can carry out loading and unloading operation of fuel in the reactor core pool area through the auxiliary loading and unloading machine. The fuel assemblies at any position of the reactor core can be accurately grasped, can be completely enveloped in the fixed sleeve and are transferred to the spent fuel assembly storage grillwork; the system and the method ensure that personnel, fuel assemblies and equipment are safe and controllable in the loading and unloading process and the technology is feasible; compared with fuel loading, unloading and storing equipment of a pressurized water reactor nuclear power station, on the premise of meeting the functional and performance requirements of deep water refueling operation, all the related equipment for refueling is simpler, higher technical maturity can be realized, and the method has stronger cost advantage.
Description
Technical Field
The invention belongs to the technical field of swimming pool type heat supply stack fuel operation, and particularly relates to a swimming pool type normal pressure low temperature heat supply stack fuel loading and unloading system and method.
Background
The swimming pool type low temperature heat supply reactor (hereinafter referred to as "low temperature reactor") is aimed at the specific requirement of nuclear energy heat supply, and the working temperature of the reactor is reasonably reduced by using the innovative technology of the deep water pool heat supply reactor, so that the heat supply reactor can work in the normal pressure deep water pool, and the reactor system and equipment are fundamentally simplified compared with the pressurized reactor. From a fuel operation perspective, it is different from pressurized water reactors in particular in terms of the following:
1. the reactor core of the low-temperature reactor and the spent fuel pool share the same factory building, and the reactor core and the spent fuel pool are communicated and isolated through the opening/closing of a water gate, so that the assembly is transported between the reactor core and the spent pool; the reactor factory building of the reactor core of the pressurized water reactor nuclear power plant is separated from the fuel factory building, and after the spent fuel assembly is discharged from the reactor core, the transportation of the fuel assembly between the reactor core and the spent fuel pool is realized through a fuel transmission channel in a refueling pool;
2. the upper tube seat of the pressurized water reactor core fuel assembly is about 12.5 meters away from the loading and unloading machine track, and the upper tube seat of the low-temperature reactor core fuel assembly is about 21 meters away from the loading and unloading machine track, so that the requirements on the grabbing and positioning of fuel are higher;
3. since the low temperature stack has no fuel transfer passage, a dedicated fuel handling device is necessary for fuel transfer.
Disclosure of Invention
The invention aims to provide a swimming pool type normal pressure low temperature heat supply reactor fuel loading and unloading system and method, which can realize the processes of reactor core refueling, spent fuel assembly transportation, storage and the like after reactor discharging, and achieve the purposes of safety, feasibility and economy.
The technical scheme of the invention is as follows: the swimming pool type normal pressure low temperature heat supply reactor fuel loading and unloading system comprises a loading and unloading machine and an underwater auxiliary loading and unloading platform, wherein the loading and unloading machine can move between a reactor core pool and a spent fuel pool which are connected with each other at will; the underwater auxiliary loading and unloading platform is arranged on the overhaul platform above the reactor core pool, and the loading and unloading machine can carry out loading and unloading operation of fuel in the reactor core pool area through the auxiliary loading and unloading machine.
The loading and unloading machine comprises a bridge rail, a cart, a trolley, a fixed sleeve and a telescopic sleeve, wherein the bridge rail is paved above a spent fuel pool and a reactor core pool; the cart can move along the bridge rail in the X direction; the rail is arranged on the cart in the horizontal Y direction perpendicular to the X direction, the cart is arranged on the rail, the grabbing component is fixedly arranged below the cart, and the grabbing component is controlled by the main lifting mechanism arranged on the cart to grab the fuel component.
The grabbing component comprises a fixed sleeve, a telescopic sleeve and a claw, wherein the fixed sleeve is fixedly arranged at the lower end of the trolley, the upper end of the telescopic sleeve positioned in the fixed sleeve is connected with the main lifting mechanism, and the claw is arranged at the lower end of the telescopic sleeve.
The cart is also provided with an auxiliary lifting mechanism which is used as auxiliary emergency equipment of the main lifting mechanism.
The underwater auxiliary loading and unloading platform comprises a guide arm and a platform base, wherein the platform base is arranged on the maintenance platform, a guide rail is arranged on the platform base, a pair of guide arms are arranged on the guide rail of the platform base, and accurate positioning of a fuel assembly below the maintenance platform is realized through movement of the guide arms on the guide rail of the platform base.
The guide arms are of a box type structure with zigzag guide holes, a driving mechanism is arranged in the guide arms, and square guide hole arrays are formed by folding the two guide arms, so that accurate and reliable guide positioning of the telescopic sleeve is realized.
The lower end surface of the fixed sleeve is higher than a sluice gate arranged between the spent fuel pool and the reactor core pool.
A fuel loading and unloading method for a swimming pool type normal pressure low temperature heat supply reactor specifically comprises the following steps:
step 1, adjusting the position of a loading and unloading machine according to the state and coordinates of a target fuel assembly, and grabbing the fuel assembly;
step 2, lifting the grabbed fuel assemblies by using a loading and unloading machine;
and 3, transferring the fuel assembly and storing the fuel assembly in a spent fuel pool grid.
The step 1 specifically comprises the following steps:
step 1.1, moving a cart and a trolley in a loading and unloading machine according to the state and the coordinates of a target fuel assembly, so that a claw at the tail end of a telescopic sleeve is positioned right above a core grabbing target position;
step 1.2, lowering the telescopic sleeve 16 to the position of the guide arm in the underwater auxiliary loading and unloading platform by adopting a low-speed, high-speed and low-speed movement mode;
step 1.3, automatically positioning by using a guide arm, and closing to form auxiliary guide for the main frame of the telescopic sleeve;
step 1.4, adopting a low-speed, high-speed and low-speed movement mode to descend the telescopic sleeve to a pre-grabbing position of the claw on the fuel assembly;
and 1.5, grabbing the fuel assembly.
The step 2 specifically includes:
step 2.1, lifting the telescopic sleeve to the action position of the guide arm of the claw in the underwater auxiliary loading and unloading platform;
step 2.2, separating the guide arms and recovering the initial positions;
step 2.3, lifting the fuel assembly into the fixed sleeve by using the telescopic sleeve in a low-speed, high-speed and low-speed movement mode.
The step 3 specifically includes:
step 3.1, moving the fixed sleeve to the position right above the storage target position of the spent fuel pool grid after passing through the sluice gate by utilizing a cart and a trolley according to the state and the coordinates of the storage target position;
step 3.2, descending the telescopic sleeve in a low-speed, high-speed and low-speed movement mode, and confirming whether the fuel assembly can be smoothly stored in the spent fuel pool storage grillwork;
3.3, descending the telescopic sleeve at a low speed to enable the fuel assembly to drop onto the bottom of the spent fuel pool storage grid, and stopping descending when the steel wire rope load sensor reaches a threshold value;
step 3.4, the driving claw is separated from the upper tube seat of the fuel assembly, and checking and confirming are carried out.
And 3.5, lifting the telescopic sleeve into the fixed sleeve in a low-speed, high-speed and low-speed mode to finish grabbing in a reactor core pool of the fuel assembly and storing in a spent fuel pool grid.
The specific steps for grabbing the fuel assembly in the step 1.5 are as follows:
step 1.5.1, confirming the relative position relation between the claw and the upper tube seat of the fuel assembly;
step 1.5.2, descending the telescopic sleeve until the telescopic sleeve is located on an upper tube seat of the fuel assembly at a low speed, and stopping descending movement when the steel wire rope load sensor reaches a threshold value;
step 1.5.3, the driving pawl is lowered and engaged with the fuel assembly upper header and checked for confirmation.
The invention has the remarkable effects that: according to the swimming pool type normal-pressure low-temperature heat supply reactor fuel loading and unloading system and method, the fuel assembly at any position of the reactor core can be accurately grabbed, can be completely enveloped in the fixed sleeve, and can be transferred to the spent fuel assembly storage grillwork; the system and the method ensure that personnel, fuel assemblies and equipment are safe and controllable in the loading and unloading process and the technology is feasible; compared with fuel loading, unloading and storing equipment of a pressurized water reactor nuclear power station, on the premise of meeting the functional and performance requirements of deep water refueling operation, all the related equipment for refueling is simpler, higher technical maturity can be realized, and the method has stronger cost advantage.
Drawings
FIG. 1 is a schematic diagram of a fuel handling system for a pool type atmospheric low temperature heating stack according to the present invention;
FIG. 2 is a schematic view of the loader-unloader of FIG. 1;
FIG. 3 is a schematic view of the structure of the underwater auxiliary loading and unloading platform in FIG. 1;
in the figure: 1. a loading and unloading machine; 2. an underwater auxiliary loading and unloading platform; 3. a maintenance platform; 4. a fuel assembly; 5. a core pool; 6. spent fuel storage grillwork; 7. spent fuel pool; 8. a sluice gate; 9. an auxiliary lifting mechanism; 10. a main lifting mechanism; 11. a control cabinet; 12. a bridge rail; 13. a trolley; 14. a cart; 15. a fixed sleeve; 16. a telescoping sleeve; 17. a gripping apparatus.
Detailed Description
The invention will be described in further detail with reference to the accompanying drawings and specific examples.
As shown in fig. 1 to 3, a swimming pool type normal pressure low temperature heat supply reactor fuel loading and unloading system comprises a loading and unloading machine 1 and an underwater auxiliary loading and unloading platform 2, wherein the loading and unloading machine 1 can move between a spent fuel pool 7 and a connected reactor core pool 5 at will, the underwater auxiliary loading and unloading platform 2 is arranged on an overhaul platform 3 above the reactor core pool 5, and the loading and unloading machine 1 can be assisted to carry out loading and unloading operations of fuel in the reactor core pool 5 through the underwater auxiliary loading and unloading platform 2; the loading and unloading machine 1 comprises a bridge rail 12, a cart 14, a trolley 13, a fixed sleeve 15 and a telescopic sleeve 16, wherein the bridge rail 12 is paved above a spent fuel pool 7 and a reactor core pool 5, the cart 14 is arranged on the bridge rail 12, so that the cart 14 can run along the bridge rail 12 in the X direction between the spent fuel pool 7 and the reactor core pool 5, and an auxiliary lifting mechanism 9 is arranged on the cart 14 and used as auxiliary emergency equipment of a main lifting mechanism 10; a track is arranged on the cart 14 along a Y direction perpendicular to the X direction of travel of the cart 14, and a trolley 13 is arranged on the track, so that the trolley can independently move along the X direction; a fixed sleeve 15 is arranged below the trolley 13, a telescopic sleeve 16 is sleeved in the fixed sleeve 15, a main lifting mechanism 10 is arranged on the trolley 13 and connected with the upper end of the telescopic sleeve 16, and the movement of the telescopic sleeve 16 along the vertical Z direction is controlled by a control cabinet 11 arranged on the trolley 13; at the end of the telescopic sleeve 16, a claw 17 is mounted for gripping the fuel assembly 4; the lowest end of the fixed sleeve 15 is higher than the sluice gate 8, after the claw 17 grabs the fuel assembly 4, the fuel assembly 4 rises together with the telescopic sleeve 16 under the action of the main lifting mechanism 10, and finally the fuel assembly 4 can be completely lifted into the fixed sleeve 15, so that the whole device can smoothly pass through the sluice gate 8; the underwater auxiliary loading and unloading platform 2 comprises a guide arm 19 and a platform base 18, wherein the platform base 18 is arranged on the maintenance platform 3, and a group of adjusting mechanisms are respectively arranged on the periphery of the bottom of the platform base 18 and can be adjusted along X, Y and Z directions in a certain range; the guide arms 19 are fixed on the guide rail of the platform base 18, so that the two guide arms 19 can move on the guide rail of the platform base 18, wherein the guide arms 19 are of a box type structure with saw-tooth-shaped guide holes, and a driving mechanism is contained in the guide arms, when the telescopic sleeve is lifted to the working elevation position of the platform, the guide arms 19 are folded to form a square guide hole array to accurately and reliably guide and position the telescopic sleeve 16; with the adjustment of the positions of the two guide arms 19, precise positioning of the fuel assemblies 4 at all positions of the core is achieved.
A fuel loading and unloading method for a swimming pool type normal pressure low temperature heat supply reactor specifically comprises the following steps:
step 1, adjusting the position of a loading and unloading machine according to the state and coordinates of a target fuel assembly, and grabbing the fuel assembly;
step 1.1, moving a cart and a trolley in a loading and unloading machine according to the state and the coordinates of a target fuel assembly, so that a claw at the tail end of a telescopic sleeve is positioned right above a core grabbing target position;
step 1.2, lowering the telescopic sleeve 16 to the position of the guide arm in the underwater auxiliary loading and unloading platform by adopting a low-speed, high-speed and low-speed movement mode;
step 1.3, automatically positioning by using a guide arm, and closing to form auxiliary guide for the main frame of the telescopic sleeve;
step 1.4, adopting a low-speed, high-speed and low-speed movement mode to descend the telescopic sleeve to a pre-grabbing position of the claw on the fuel assembly;
step 1.5, grabbing the fuel assembly;
step 1.5.1, confirming the relative position relation between the claw and the upper tube seat of the fuel assembly;
step 1.5.2, descending the telescopic sleeve until the telescopic sleeve is located on an upper tube seat of the fuel assembly at a low speed, and stopping descending movement when the steel wire rope load sensor reaches a threshold value;
step 1.5.3, the driving claw is lowered and meshed with the upper tube seat of the fuel assembly, and checking and confirming;
step 2, lifting the grabbed fuel assemblies by using a loading and unloading machine;
step 2.1, lifting the telescopic sleeve to the action position of the guide arm of the claw in the underwater auxiliary loading and unloading platform;
step 2.2, separating the guide arms and recovering the initial positions;
step 2.3, lifting the fuel assembly into the fixed sleeve by using the telescopic sleeve in a low-speed, high-speed and low-speed movement mode;
step 3, transferring the fuel assembly and storing the fuel assembly in a spent fuel pool grid;
step 3.1, moving the fixed sleeve to the position right above the storage target position of the spent fuel pool grid after passing through the sluice gate by utilizing a cart and a trolley according to the state and the coordinates of the storage target position;
step 3.2, descending the telescopic sleeve in a low-speed, high-speed and low-speed movement mode, and confirming whether the fuel assembly can be smoothly stored in the spent fuel pool storage grillwork;
3.3, descending the telescopic sleeve at a low speed to enable the fuel assembly to drop onto the bottom of the spent fuel pool storage grid, and stopping descending when the steel wire rope load sensor reaches a threshold value;
step 3.4, the driving claw is separated from the upper tube seat of the fuel assembly, and checking and confirming are carried out.
And 3.5, lifting the telescopic sleeve into the fixed sleeve in a low-speed, high-speed and low-speed mode to finish grabbing in a reactor core pool of the fuel assembly and storing in a spent fuel pool grid.
Claims (10)
1. A swimming pool type normal pressure low temperature heat supply fuel loading and unloading system is characterized in that: the system comprises a loading and unloading machine (1) and an underwater auxiliary loading and unloading platform (2), wherein the loading and unloading machine (1) can move between a reactor core pool (5) and a spent fuel pool (7) which are connected with each other at will; the underwater auxiliary loading and unloading platform (2) is arranged on the overhaul platform (3) above the reactor core water tank (5), and the loading and unloading machine (1) can carry out loading and unloading operation of fuel in the area of the reactor core water tank (5) through the auxiliary loading and unloading machine (1); the loading and unloading machine (1) comprises a bridge rail (12), a cart (14), a trolley (13), a fixed sleeve (15) and a telescopic sleeve (16), wherein the bridge rail (12) is paved above a spent fuel pool (7) and a reactor core pool (5); the cart (14) can move along the bridge rail (12) in the X direction; a track is arranged on the cart (14) in the horizontal Y direction perpendicular to the X direction, a trolley (13) is arranged on the track, a grabbing component is fixedly arranged below the trolley (13), and the grabbing component is controlled by a main lifting mechanism (10) arranged on the trolley (13) to grab the fuel component; the underwater auxiliary loading and unloading platform (2) comprises a guide arm (19) and a platform base (18), wherein the platform base (18) is arranged on the overhauling platform (3), a guide rail is arranged on the platform base (18), a pair of guide arms (19) are arranged on the guide rail of the platform base (18), and the accurate positioning of the fuel assembly (4) below the overhauling platform (3) is realized through the movement of the guide arms (19) on the guide rail of the platform base (18).
2. A pool type atmospheric low temperature heating stack fuel handling system as defined in claim 1 wherein: the grabbing component comprises a fixed sleeve (15), a telescopic sleeve (16) and a claw (17), wherein the fixed sleeve (15) is fixedly arranged at the lower end of the trolley (13), the upper end of the telescopic sleeve (16) positioned in the fixed sleeve (15) is connected with the main lifting mechanism (10), and the claw (17) is arranged at the lower end of the telescopic sleeve (16).
3. A pool type atmospheric low temperature heating stack fuel handling system as defined in claim 1 wherein: the cart (14) is also provided with an auxiliary lifting mechanism (9) which is used as auxiliary emergency equipment of the main lifting mechanism (10).
4. A pool type atmospheric low temperature heating stack fuel handling system as defined in claim 1 wherein: the guide arms (19) are of a box type structure with zigzag guide holes, a driving mechanism is arranged in the guide arms, and square guide hole arrays are formed by folding the two guide arms (19), so that accurate and reliable guide positioning of the telescopic sleeve (16) is realized.
5. A pool type atmospheric low temperature heating stack fuel handling system as defined in claim 2 wherein: the lower end surface of the fixed sleeve (15) is higher than a sluice gate (8) arranged between the spent fuel pool (7) and the reactor core pool (5).
6. A method of loading and unloading a fuel loading and unloading system using a pool type atmospheric low temperature heating stack as defined in any one of claims 1 to 5, characterized in that: the method specifically comprises the following steps:
step 1, adjusting the position of a loading and unloading machine according to the state and coordinates of a target fuel assembly, and grabbing the fuel assembly;
step 2, lifting the grabbed fuel assemblies by using a loading and unloading machine;
and 3, transferring the fuel assembly and storing the fuel assembly in a spent fuel pool grid.
7. The method for loading and unloading a pool type atmospheric low temperature heating stack fuel loading and unloading system according to claim 6, wherein: the step 1 specifically comprises the following steps:
step 1.1, moving a cart and a trolley in a loading and unloading machine according to the state and the coordinates of a target fuel assembly, so that a claw at the tail end of a telescopic sleeve is positioned right above a core grabbing target position;
step 1.2, a low-speed, high-speed and low-speed movement mode is adopted, and the telescopic sleeve is put down to the position of the guide arm in the underwater auxiliary loading and unloading platform;
step 1.3, automatically positioning by using a guide arm, and closing to form auxiliary guide for the main frame of the telescopic sleeve;
step 1.4, adopting a low-speed, high-speed and low-speed movement mode to descend the telescopic sleeve to a pre-grabbing position of the claw on the fuel assembly;
and 1.5, grabbing the fuel assembly.
8. The method for loading and unloading a pool type atmospheric low temperature heating stack fuel loading and unloading system according to claim 6, wherein: the step 2 specifically includes:
step 2.1, lifting the telescopic sleeve to the action position of the guide arm of the claw in the underwater auxiliary loading and unloading platform;
step 2.2, separating the guide arms and recovering the initial positions;
step 2.3, lifting the fuel assembly into the fixed sleeve by using the telescopic sleeve in a low-speed, high-speed and low-speed movement mode.
9. The method for loading and unloading a pool type atmospheric low temperature heating stack fuel loading and unloading system according to claim 6, wherein: the step 3 specifically includes:
step 3.1, moving the fixed sleeve to the position right above the storage target position of the spent fuel pool grid after passing through the sluice gate by utilizing a cart and a trolley according to the state and the coordinates of the storage target position;
step 3.2, descending the telescopic sleeve in a low-speed, high-speed and low-speed movement mode, and confirming whether the fuel assembly can be smoothly stored in the spent fuel pool storage grillwork;
3.3, descending the telescopic sleeve at a low speed to enable the fuel assembly to drop onto the bottom of the spent fuel pool storage grid, and stopping descending when the steel wire rope load sensor reaches a threshold value;
step 3.4, separating the driving claw from the upper tube seat of the fuel assembly, and checking and confirming;
and 3.5, lifting the telescopic sleeve into the fixed sleeve in a low-speed, high-speed and low-speed mode to finish grabbing in a reactor core pool of the fuel assembly and storing in a spent fuel pool grid.
10. A method of loading and unloading a pool type atmospheric low temperature heating stack fuel loading and unloading system as defined in claim 7, wherein: the specific steps for grabbing the fuel assembly in the step 1.5 are as follows:
step 1.5.1, confirming the relative position relation between the claw and the upper tube seat of the fuel assembly;
step 1.5.2, descending the telescopic sleeve until the telescopic sleeve is located on an upper tube seat of the fuel assembly at a low speed, and stopping descending movement when the steel wire rope load sensor reaches a threshold value;
step 1.5.3, the driving pawl is lowered and engaged with the fuel assembly upper header and checked for 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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| 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 true CN109979626B (en) | 2024-04-09 |
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| 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 |
| 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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