CN114446498A - Centering device for nuclear power station reactor pressure vessel in-place - Google Patents
Centering device for nuclear power station reactor pressure vessel in-place Download PDFInfo
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- CN114446498A CN114446498A CN202011214504.5A CN202011214504A CN114446498A CN 114446498 A CN114446498 A CN 114446498A CN 202011214504 A CN202011214504 A CN 202011214504A CN 114446498 A CN114446498 A CN 114446498A
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- pressure vessel
- reactor pressure
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/024—Supporting constructions for pressure vessels or containment vessels
-
- 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)
- Pressure Vessels And Lids Thereof (AREA)
Abstract
The invention belongs to a centering device, and particularly relates to a nuclear power station reactor pressure vessel in-position centering device. A centering device for positioning a reactor pressure vessel of a nuclear power station comprises the reactor pressure vessel, a support frame, a guide adjusting tool and a guide device support ring. The invention has the following remarkable effects: the operation is simple, the equipment is prevented from being scratched and damaged, and the installation quality is ensured; the construction efficiency can be improved, narrow-gap in-place equipment can be solved, the disassembly and assembly are very convenient, and the storage space is greatly saved.
Description
Technical Field
The invention belongs to a centering device, and particularly relates to a nuclear power station reactor pressure vessel in-position centering device.
Background
In the installation and construction of the nuclear power generating unit, the reactor pressure vessel is hoisted in place at the center of a nuclear island plant by a ring crane. The maximum external dimension of the reactor pressure vessel is 6965mm multiplied by 6407mm multiplied by 9454.2mm, the diameter of the cylinder body is phi 4870mm, the hoisting weight is about 330t, and the reactor pressure vessel belongs to nuclear island heavy key equipment and has high positioning requirement precision. In the hoisting and positioning project of the reactor pressure vessel of the CPR1000/VVER/ERP1000 nuclear power unit, the reactor pressure vessel is ensured to coincide with the center of a nuclear island plant by the rotation of a ring crane cart, the horizontal movement of a ring crane trolley and the transverse movement of a ring crane hook. The 550t lifting hook of the ring crane mounting trolley for hoisting the reactor pressure vessel in place of Hualong I is not designed with a transverse translation mechanism, and the superposition of the reactor pressure vessel and the center of a nuclear island plant cannot be guaranteed only by the rotation of the ring crane cart and the horizontal movement of the ring crane trolley due to the influence of civil engineering foundation and ring crane mounting deviation. The following risks exist during the hoisting and in-place construction of the reactor pressure vessel:
1) the reactor pressure vessel deviates from the installation position and cannot be in place;
2) and when the reactor pressure vessel is in the position, the reactor pressure vessel is in heat preservation and is scraped with the periphery.
Disclosure of Invention
The invention aims at the defects of the prior art and provides a nuclear power station reactor pressure vessel positioning and centering device.
The invention is realized by the following steps: a centering device for positioning a reactor pressure vessel of a nuclear power station comprises the reactor pressure vessel, a support frame, a guide adjusting tool and a guide device support ring.
According to the centering device for positioning the reactor pressure vessel of the nuclear power station, the support frame consists of a cross beam I, a bolt I, a support leg, a connecting plate I, a bolt II, a cross beam II and a connecting plate II.
The centering device for positioning the reactor pressure vessel of the nuclear power station is characterized in that the cross beam I: the carbon steel pipe is manufactured by processing a carbon steel pipe with the diameter of 30mm by 190mm, and mainly aims to connect two supporting legs by using two ends;
bolt I: the bolt and the nut with the specification of M12 have the functions of locking the connecting plate, the support frame can be used after the connecting plate is locked by a wrench, and the bolt can be loosened after the support frame is used, so that the deformation condition is avoided;
supporting legs: 4 stainless steel pipes with the diameter of 48mm by 570mm are processed and manufactured, and the main supporting function is realized in the whole supporting frame;
the connecting plate I is manufactured by machining a stainless steel plate with the width of 50mm and the length of 245mm and drilling a hole on the stainless steel plate
One is
The holes are respectively used for connecting the supporting legs and the connecting plate;
and B, bolt II: the bolt and the nut with the specification of M10 are used for locking the connecting plate;
and a beam II: the carbon steel pipe is manufactured by processing a carbon steel pipe with the diameter of 30mm and the length of 330 mm, and mainly aims to connect supporting legs by using two ends;
and (5) connecting a plate II: machining from a 50mm wide by 150mm stainless steel plate and drilling a hole therein
One is
The holes are respectively used for connecting the supporting legs and the connecting plate;
when the support frame is contracted, all the bolts are loosened, the horizontal ground is placed for expansion, after the bolts are completely expanded, all the bolts are screwed down, and the support ring is placed on the support frame for working.
The centering device for positioning the reactor pressure vessel of the nuclear power station comprises a hand wheel, an M30 adjusting jackscrew, a jackscrew bracket, a bottom plate, an L-shaped sliding groove, a jackscrew supporting plate, a baffle plate, an M8 fixing bolt, a sliding plate and a guide wheel assembly.
The centering device for positioning the reactor pressure vessel of the nuclear power station comprises a guide wheel support plate, a guide wheel side support plate, a rubber wheel with a rolling bearing and a shaft.
According to the centering device for positioning the reactor pressure vessel of the nuclear power station, the L-shaped sliding groove is connected with the bottom plate in a welding mode to form the sliding way, so that the sliding plate is limited in moving. The jackscrew bracket is connected with the bottom plate in a welding mode and is used for providing support for adjusting the jackscrew. 4 long screw holes are formed in the bottom plate, so that the whole in-place guiding and adjusting tool is convenient to fix.
The centering device for positioning the reactor pressure vessel of the nuclear power station is characterized in that the guide device support ring comprises three circular tubes with the diameter of 48mm and the wall thickness of 3mm, and the cross beam is formed by the three circular tubes.
The invention has the following remarkable effects: 1) the invention has simple thought and simple operation, all the components of the device to be manufactured are common sectional materials frequently used in a construction site, except that corresponding screws need to be purchased and manufactured, the manufacture of other parts can be realized by using local materials, the manufacture can be completed by using the residual materials, and the investment cost is low;
2) according to the invention, the reactor pressure vessel can be accurately positioned after the ring-shaped lifting hook cancels the transverse translation function, so that the equipment is prevented from being scratched and damaged, and the installation quality is ensured.
3) The installation is simple to use, only needs the bolt fastening can use, rotates the hand wheel during the use and can realize the function.
4) The construction efficiency can be improved, the equipment can be adjusted while being in place, the success of one-time in-place can be realized, the success rate of in-place of the equipment is greatly improved, and the repeated adjustment times are reduced.
5) The problem that narrow-gap in-place equipment cannot be centered by a crane can be solved, the construction difficulty is solved, the construction quality is improved, and the safety risk is reduced.
6) The whole parts have the dismounting and mounting moving capability, the occupation of excessive storage space is avoided, the dismounting and mounting are very convenient, and the storage space is greatly saved.
Drawings
FIG. 1: the reactor pressure vessel is in-position and centered;
FIG. 2: structure of reactor pressure vessel guiding device support frame that takes one's place
FIG. 3: retracted view of the support
FIG. 4: stereogram of positioning guiding adjusting tool structure
FIG. 5: guide wheel assembly structure diagram
FIG. 6 schematic view of a support ring
Wherein: s1, a reactor pressure vessel, S2, a support frame, S3, a guide adjusting tool, S4, a guide device support ring, S201, a beam I, S202, a bolt I, S203, a support leg, S204, a connecting plate I, S205, a bolt II, S206, a beam II, S207, a connecting plate II, S301, a hand wheel, S302, an adjusting jackscrew, S304, a base, S309, a sliding plate, S310, a guide wheel, S401, a round tube, S402, a round tube, S403, an anchoring plate, S404, a bolt hole, S405, a fixing plate
Detailed Description
The invention belongs to the field of nuclear power installation, and particularly relates to a reactor pressure vessel hoisting in-place construction operation.
The invention mainly utilizes a nuclear island plant structure to fix a reactor pressure vessel guiding and positioning device in a reactor cavity, and a sliding adjusting device is rotated to adjust a screw rod to push a sliding block, so that the reactor pressure vessel is pushed to displace and coincide with the center of the nuclear island plant.
The invention is suitable for accurately positioning the reactor pressure vessel to the center of the reactor cavity in the installation process of the nuclear island and coinciding with the center of a plant of the nuclear island. The integral structure of the reactor pressure vessel (S1) positioning guide device is shown in figure 1.
The structure of the reactor pressure vessel position guide device support frame (S2) is shown in figure 2.
The reactor pressure vessel guiding device support frame (S2) that takes one' S place comprises crossbeam I (S201), bolt I (S202), landing leg (S203), connecting plate I (S204), bolt II (S205), crossbeam II (S206), connecting plate II (S207).
Beam i (S201): the carbon steel pipe is processed and manufactured by carbon steel pipes with the diameter of 30mm by 190mm, and the main purpose is to connect two supporting legs by using two ends (S203);
bolt i (S202): the bolt and the nut with the specification of M12 have the effects of locking the connecting plate, using the support frame (S2) after the connecting plate is locked by a spanner, and loosening the bolt after the use is finished, so that the deformation condition is avoided;
leg (S203): 4 stainless steel pipes with the diameter of 48mm by 570mm are processed and manufactured, and the main supporting function is realized in the whole supporting frame;
connecting plate I (S204) is made of a stainless steel plate 50mm wide by 245mm long and drilled with a hole
One is
Respectively used for connecting the supporting leg (S203) and the connecting plate (S207);
bolt ii (S205): the bolt and the nut with the specification of M10 are used for locking the connecting plate (S204);
beam ii (S206): the carbon steel pipe is processed and manufactured by a carbon steel pipe with the diameter of 30mm and the length of 330 mm, and the main purpose is to connect supporting legs by using two ends (S203);
connection plate ii (S207): machining from a 50mm wide by 150mm stainless steel plate and drilling one thereon
One is
Respectively used for connecting the supporting leg (S203) and the connecting plate (S204);
when the support frame is contracted, all the bolts (S202) are unscrewed, the support frame is placed on a horizontal ground to be unfolded, after the support frame is completely unfolded, all the bolts (S202) are screwed, and the support ring (S4) is placed on the support frame (S2) to work.
After the use is finished, the pressure vessel positioning guide tool (S3) is lifted away from the support ring (S4), the support ring (S4) is placed at the same time, the bolt (S202) of the support frame is loosened, and the support frame can be contracted through manpower
The support frame (S2) is matched with a spanner for use when being unfolded and contracted.
Structure of guide adjustment tool (S3)
The guide adjusting tool mainly comprises a hand wheel (S301), an adjusting jackscrew (S302), a base (S304), a sliding plate (S309) and a guide wheel (S310).
Guiding and adjusting the tool: the device is composed of a hand wheel (S301), an M30 adjusting jackscrew (S302), a jackscrew bracket (S303), a bottom plate (S304), an L-shaped sliding groove (S305), a jackscrew supporting plate (S306), a baffle (S307), an M8 fixing bolt (S308), a sliding plate (S309) and a guide wheel assembly (S310).
Guide wheel assembly (S310): the guide wheel assembly is composed of a guide wheel supporting plate (101), a guide wheel side supporting plate (102), a rubber wheel (103) with a rolling bearing and a shaft (104), all parts of the guide wheel assembly are connected in a welding mode, and the guide wheel assembly is stable in structure.
The L-shaped sliding groove (S305) is connected with the bottom plate (S304) in a welding mode to form a sliding way, so that the sliding plate (S309) is limited in movement. The jackscrew bracket (S303) is connected with the bottom plate (S304) in a welding mode and is used for providing support for the adjusting jackscrew (S302). 4 long screw holes are formed in the bottom plate (S304), so that the whole in-place guiding and adjusting tool can be conveniently fixed.
When the guide adjusting tool is used, the guide wheel (S310) is moved back and forth by rotating the hand wheel (S301), the guide wheel (S310) is in contact with equipment, the equipment can be pushed to perform centering adjustment, meanwhile, in the falling process of the equipment, the guide wheel (S310) can keep the thrust on the equipment and keep rolling, the guide effect can be achieved, and the rubber wheel (103) with the rolling bearing cannot damage the surface of the equipment.
Structure of reactor pressure vessel seating guide support ring (S4)
Support ring (S4): the cross beam is composed of three circular tubes (S401) with the diameter of 48mm and the wall thickness of 3mm, and the circular tubes are inconvenient to bend in a large radian, so that a method of dividing angles in a segmented mode is adopted, the fact that the whole use cannot be influenced by the uniform stress of each circular tube is guaranteed, and the diameter of a circular ring which needs to be formed by a certain radian is guaranteed. Then, in order to maintain stability, a circular tube (S402) with the diameter of 30mm and the wall thickness of 2mm is added among the three beams for supporting the beams. And when a huge ring is finally formed, an anchoring plate (S403) with the thickness of 10mm needs to be used for connection and fastening, so that the use safety is ensured. This is the integral support ring attachment. Furthermore, three M10 bolt holes are formed in each anchoring plate (S404), and the supporting ring is directly fastened and connected through the bolts. The construction and use are convenient, the storage can be disassembled and stored during storage, and the occupied space is reduced. And there is a welding fixing plate (S405) on the integrated support ring segment, which is a fixing position of the position guide adjusting tool. 4 threaded holes are made in the plate and the guide adjustment tool is locked to the support ring with bolts (S406).
The using method comprises the following steps:
1) and (S2) 12 support frames of the reactor pressure vessel positioning guide device are uniformly arranged at the reactor positioning cavity position of the reactor pressure vessel cylinder (S1).
2) And assembling the support ring (S4) on the support frame (S2) by using bolts, wherein the fixing plate is positioned at the axial positions of 60 degrees, 180 degrees and 300 degrees of the reactor factory building.
3) In the process of introducing the reactor pressure vessel cylinder (S1) into the reactor pit, when the hand wheel (1) is rotated, the guide wheel assembly (10) is in contact with the reactor pressure vessel cylinder (S1), 3 sets of in-position guide adjusting tools (S3) are used simultaneously, and the pressure vessel is pushed to be aligned with the reactor core.
4) The gap between the pressure vessel cylinder and the heat-insulating layer of the peripheral cylinder is ensured to be consistent, the pressure vessel is in place by virtue of the guiding function of the tool, and the pressure vessel is prevented from colliding with the heat-insulating layer.
The device can be directly used for the installation and construction operation of the Hualongyi reactor pressure vessel. The method can solve the problem that the pressure vessel and the reactor core cannot be centered when the pressure vessel is hoisted by a ring crane, can realize the in-place centering of the pressure vessel and in-place adjustment while in-place, can not damage the cylinder body of the pressure vessel, ensures the quality of the installation and construction of the pressure vessel, and has remarkable benefit.
Claims (7)
1. A centering device that takes one's place of nuclear power station reactor pressure vessel which characterized in that: the reactor pressure vessel support device comprises a reactor pressure vessel (S1), a support frame (S2), a guide adjusting tool (S3) and a guide device support ring (S4).
2. The centering device for positioning the reactor pressure vessel in the nuclear power plant as claimed in claim 1, wherein: the support frame (S2) comprises a beam I (S201), a bolt I (S202), a support leg (S203), a connecting plate I (S204), a bolt II (S205), a beam II (S206) and a connecting plate II (S207).
3. The centering device for positioning the reactor pressure vessel of the nuclear power plant as claimed in claim 2, wherein: the beam I (S201): the carbon steel pipe is processed and manufactured by carbon steel pipes with the diameter of 30mm by 190mm, and the main purpose is to connect two supporting legs by using two ends (S203);
bolt i (S202): the bolt and the nut with the specification of M12 have the effects of locking the connecting plate, using the support frame (S2) after the connecting plate is locked by a spanner, and loosening the bolt after the use is finished, so that the deformation condition is avoided;
leg (S203): 4 stainless steel pipes with the diameter of 48mm by 570mm are processed and manufactured, and the main supporting function is realized in the whole supporting frame;
connecting plate I (S204) is made of a stainless steel plate 50mm wide by 245mm long and drilled with a hole
One is
Respectively used for connecting the supporting leg (S203) and the connecting plate (S207);
bolt ii (S205): the bolt and the nut with the specification of M10 are used for locking the connecting plate (S204);
beam ii (S206): the carbon steel pipe is processed and manufactured by a carbon steel pipe with the diameter of 30mm and the length of 330 mm, and the main purpose is to connect supporting legs by using two ends (S203);
connection plate ii (S207): machining from a 50mm wide by 150mm stainless steel plate and drilling one thereon
One is
Respectively used for connecting the supporting leg (S203) and the connecting plate (S204);
when the support frame is contracted, all the bolts (S202) are unscrewed, the support frame is placed on a horizontal ground to be unfolded, after the support frame is completely unfolded, all the bolts (S202) are screwed, and the support ring (S4) is placed on the support frame (S2) to work.
4. A nuclear power plant reactor pressure vessel in-position centering device as claimed in claim 3, wherein: the guide adjusting tool (S3) is composed of a hand wheel (S301), an M30 adjusting jackscrew (S302), a jackscrew bracket (S303), a bottom plate (S304), an L-shaped sliding groove (S305), a jackscrew supporting plate (S306), a baffle plate (S307), an M8 fixing bolt (S308), a sliding plate (S309) and a guide wheel assembly (S310).
5. The centering device for positioning of the reactor pressure vessel of the nuclear power plant as claimed in claim 4, wherein: the guide wheel assembly (S310) consists of a guide wheel support plate (101), a guide wheel side support plate (102), a rubber wheel (103) with a rolling bearing and a shaft (104).
6. The centering device for positioning the reactor pressure vessel of the nuclear power plant as recited in claim 5, wherein: the L-shaped sliding groove (S305) is connected with the bottom plate (S304) in a welding mode to form a sliding way, so that the sliding plate (S309) is limited in movement. The jackscrew bracket (S303) is connected with the bottom plate (S304) in a welding mode and is used for providing support for the adjusting jackscrew (S302). 4 long screw holes are formed in the bottom plate (S304), so that the whole in-place guiding and adjusting tool can be conveniently fixed.
7. The centering device for positioning of the reactor pressure vessel of the nuclear power plant as claimed in claim 6, wherein: the guide device support ring (S4) is composed of a cross beam consisting of three circular tubes (S401) with the diameter of 48mm and the wall thickness of 3 mm.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011214504.5A CN114446498A (en) | 2020-11-04 | 2020-11-04 | Centering device for nuclear power station reactor pressure vessel in-place |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011214504.5A CN114446498A (en) | 2020-11-04 | 2020-11-04 | Centering device for nuclear power station reactor pressure vessel in-place |
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| CN114446498A true CN114446498A (en) | 2022-05-06 |
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| CN202011214504.5A Pending CN114446498A (en) | 2020-11-04 | 2020-11-04 | Centering device for nuclear power station reactor pressure vessel in-place |
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