CN105609148B - Device for precision control of embedded assembly of push-pull device of nuclear power plant and installation method - Google Patents
Device for precision control of embedded assembly of push-pull device of nuclear power plant and installation method Download PDFInfo
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- CN105609148B CN105609148B CN201510990702.3A CN201510990702A CN105609148B CN 105609148 B CN105609148 B CN 105609148B CN 201510990702 A CN201510990702 A CN 201510990702A CN 105609148 B CN105609148 B CN 105609148B
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- embedded
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
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- E—FIXED CONSTRUCTIONS
- E04—BUILDING
- E04G—SCAFFOLDING; FORMS; SHUTTERING; BUILDING IMPLEMENTS OR AIDS, OR THEIR USE; HANDLING BUILDING MATERIALS ON THE SITE; REPAIRING, BREAKING-UP OR OTHER WORK ON EXISTING BUILDINGS
- E04G21/00—Preparing, conveying, or working-up building materials or building elements in situ; Other devices or measures for constructional work
- E04G21/14—Conveying or assembling building elements
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
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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
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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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- Architecture (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Mechanical Engineering (AREA)
- Civil Engineering (AREA)
- Structural Engineering (AREA)
- Conveying And Assembling Of Building Elements In Situ (AREA)
Abstract
The invention discloses a device and an installation method for controlling precision of a pre-embedded assembly of a push-pull device of a nuclear power plant. The installation steps are as follows: binding a reactor core cylindrical concrete wallboard reinforcing mesh; installing a push-pull device embedded sleeve assembly, performing precision adjustment on the embedded sleeve assembly, and fixing the push-pull device embedded sleeve assembly; installing an embedded plate; pouring a core concrete wall; and installing guide rails on the embedded plates, and adjusting the precision of the guide rails. The invention solves the problems of cross collision and difficult construction between the embedded components of the push-pull device and the dense steel bar meshes and other embedded items in the concrete wall; the control requirement of the elevation parallelism tolerance (less than 1mm) of the pre-embedded assembly of the push-pull device is met; the requirement of vertical coplanarity of the axis of the push-pull device is met, and the push-pull device is convenient to operate flexibly.
Description
Technical Field
The invention belongs to the field of design and construction of nuclear power plants, and particularly relates to a device for precision control of a pre-embedded assembly of a push-pull device of a nuclear power plant and an installation method.
Background
The push-pull device of the out-of-core detector on the primary shielding wall of the nuclear reactor core is mechanical equipment for installing and replacing the detector through a neutron detector of a horizontal moving nuclear measuring instrument system, the push-pull device can easily move back and forth along the horizontal direction by ensuring single arm strength, and the push-pull device needs to penetrate through the primary shielding wall through a sleeve. The primary shielding wall peripheral floor is required to be provided with an embedded plate for the pulley walking of the push-pull device. The nuclear grade anti-seismic I-type primary shielding wall plays an extremely important role in radiation shielding protection and structural seismic resistance of a reactor, the primary shielding wall is cylindrical with a thickness of 1-2.5 m and a longitudinal variable cross section, the reinforcing bars of the primary shielding wall are irregular and very dense in shape, the reinforcing bars are annularly arranged on one side and have a distance of 100mm between two layers and a distance of 100mm between two layers in a longitudinal direction, and the construction difficulty of the wall reinforcing bar engineering is high. Besides intensive reinforcement, the primary shielding wall also has push-pull device sleeves, steel cladding, nuclear detection sleeves, ventilation direct-buried pipes, main pipelines and pressure vessel fixing bolts, and numerous items are difficult to construct in a crossed manner. The sleeve of the push-pull device is longitudinally variable in cross section, the pipe diameter is about 100mm, the length is about 1500mm, the tolerance requirement of the horizontal parallelism of the upper sleeve, the lower sleeve and the floor embedded plate is 1mm, and the precision requirement is extremely high.
The previous engineering example shows that the embedded part of the push-pull device is seriously collided with the wall reinforcing steel bar net piece when being installed, cannot be installed and is difficult to process; and the precision of the embedded part of the push-pull device can not meet the requirement, the traveling direction of the pulley of the push-pull device is not easy to control, and the use is inconvenient. Therefore, it is necessary to provide a device for controlling the precision of the embedded component of the push-pull device in the nuclear power plant and a corresponding installation method, so as to meet the requirement of precision control of the embedded component of the push-pull device and facilitate use.
Disclosure of Invention
The invention aims to provide a device for controlling the precision of an embedded component of a push-pull device of a nuclear power plant, and solves the problem that the embedded part of the push-pull device is difficult to install and control the precision.
In order to achieve the purpose, the technical scheme of the invention is that the device for controlling the precision of the embedded assembly of the push-pull device of the nuclear power plant comprises an embedded sleeve assembly of the push-pull device, an embedded plate and an adjusting guide rail.
As an improvement of the precision control of the embedded assembly of the push-pull device of the nuclear power plant, the embedded sleeve assembly of the push-pull device comprises embedded sleeves, an outer steel panel and a precision detachable adjusting support, wherein the outer steel panel is used for integrally connecting the embedded sleeves, and the precision detachable adjusting support is used for adjusting the embedded sleeves.
As an improvement of the precision control of the pre-buried assembly of the push-pull device of the nuclear power plant, the pre-buried plate and the adjusting guide rail comprise guide rails for fixing the traveling direction of pulleys of the push-pull device, connecting bolts of the guide rails and the pre-buried plate, and guide rail limiting blocks.
In order to realize the invention, the invention provides an installation method of a precision control device of a pre-embedded assembly of a push-pull device of a nuclear power plant, which comprises the following steps: binding a reinforcing mesh of a peripheral floor slab of the primary shielding wall; installing an embedded plate; and (5) pouring a concrete floor. Binding a reinforcing mesh of a reactor core cylindrical concrete wall; installing a push-pull device embedded sleeve assembly, performing precision adjustment on the embedded sleeve assembly through a detachable adjusting support, and fixing the push-pull device embedded sleeve assembly; and (5) pouring the core concrete wall. And installing a guide rail on the embedded plate, adjusting the precision of the guide rail, and rechecking the embedded sleeve assembly of the push-pull device to meet the parallelism requirement with the precision of the guide rail.
The invention has the following effects: (1) the push-pull device embedded sleeve assembly is prefabricated on a lathe platform of a factory, and the parallelism precision requirement among all sleeves of the assembly can be effectively guaranteed. (2) The detachable adjusting support of the push-pull device embedded sleeve assembly can be detached during field construction and installation, so that the embedded sleeve assembly is prevented from being in cross collision with dense steel bar meshes and other embedded items in a concrete wall, the embedded sleeve assembly is convenient to install in place, and the adjusting support is reset after the embedded sleeve assembly is in place to adjust the precision of the embedded sleeve assembly. (3) The adjusting guide rails are arranged on the embedded plate and the pulley block of the push-pull device, the traveling direction of the pulley of the push-pull device is fixed, the requirement of vertical coplanarity of the axis of the push-pull device is met, the embedded sleeve assembly of the push-pull device and the precision of the guide rails are adjusted by adjusting the precision of the guide rails, and the push-pull device is convenient to operate flexibly.
Drawings
FIG. 1 is an elevation view of a primary shield wall panel of a reactor core
FIG. 2 is a cross-sectional view of a pre-embedded assembly of a push-pull device on a primary shield wall
FIG. 3 is a detailed view of the push-pull device pre-embedded sleeve assembly
FIG. 4 is a detailed view of the connection between the detachable adjustable support and the embedded sleeve
FIG. 5 is a plan view of the pre-buried plate and the adjusting guide rail of the push-pull device
FIG. 6 is a cross-sectional view of the pre-buried plate and the adjusting guide rail of the push-pull device
In the figure, 1-embedded casing, 2-steel panel, 3-embedded plate, 4-guide rail, 5-primary shielding wall, 6-peripheral floor slab, 7-primary shielding wall reinforcement, 8-angle steel, 9-basket bolt, 10-hoop, 11-gasket, 12-angle steel connecting piece, 13-nut a, 14-cushion block, 15-bolt, 16-perforation plug welding, 17-guide rail cushion plate, 18-nut b, 19-pulley, 20-push-pull mechanical device and 21-wedge-shaped guide rail limiting block.
Detailed Description
The invention will be further described with reference to the accompanying figures 1 to 6 and examples.
Step 1, prefabricating a pre-buried sleeve 1 in a factory and welding the pre-buried sleeve with a steel panel 2 to meet the requirement that the central line of the sleeve is vertically coplanar; the angle steel 8 is welded with the turnbuckle bolt 9, and the angle steel 8 is welded with the angle steel connecting piece 12 to form a detachable adjusting support; the embedded sleeves and the detachable adjusting supports are connected through the anchor ears 10, the parallelism of the central lines of the two embedded sleeves is adjusted through the quantity of the adjusting gaskets 11 and the threads of the turnbuckle bolts 9, the requirement that the horizontal parallelism tolerance is less than or equal to 1mm is met, and the nuts a13 are screwed.
And 2, prefabricating the embedded plate 3 in a factory, and connecting the bolt 15 with the embedded plate 3 through a perforated plug weld 16.
And 3, installing the embedded plate 3 on the peripheral floor 6 on site, and adjusting the center line and the elevation of the embedded plate 3. And pouring concrete of the peripheral floor 6.
And 5, welding the guide rail 4 and the rail backing plate 17, penetrating through a bolt hole in the rail backing plate 17, connecting the rail backing plate 17 with the embedded plate 3 through a bolt 15, adjusting a cushion block 14, rechecking the parallelism of the center line of the guide rail 4 and the center line of the sleeve 1, meeting the tolerance requirement of less than or equal to 1mm of horizontal parallelism, adjusting to meet the requirement that the center line of the guide rail 4 and the center line of the sleeve 1 are vertically coplanar, and screwing a nut b 18.
And 6, the push-pull mechanical device 20 travels to a required position in the determined direction of the guide rail 4 through the pulley 19, and the wedge-shaped guide rail limiting block 21 is placed in the guide rail 4 to fix the position of the push-pull mechanical device 20.
While the embodiments of the present invention have been described in detail, the above embodiments are merely preferred embodiments of the present invention, but the present invention is not limited to the above embodiments, and various changes can be made within the knowledge of those skilled in the art without departing from the gist of the present invention.
Claims (8)
1. A device for controlling precision of a pre-buried assembly of a push-pull device of a nuclear power plant is characterized by comprising a pre-buried sleeve assembly of the push-pull device, a pre-buried plate and a guide rail;
the push-pull device embedded assembly is positioned in the concrete base material; one side of the embedded sleeve assembly of the push-pull device is welded and connected into a whole through an outer steel panel; the other side of the push-pull device embedded sleeve assembly is connected through a detachable adjusting support; the push-pull device embedded sleeve assembly comprises a plurality of sleeves;
the embedded plate of the push-pull device is welded with the guide rail through bolt penetration, and the pulley of the push-pull device is positioned on the guide rail, so that the requirement of vertical coplanarity of the axis of the embedded assembly of the push-pull device is met;
the detachable adjusting support is connected with the sleeve through an anchor ear, and a rigid gasket is arranged between the anchor ear and the sleeve to realize fine adjustment of the parallelism of the central line of the sleeve;
a rigid cushion block is arranged between the guide rail base plate and the embedded plate, so that fine adjustment of the parallelism of the center line of the guide rail is realized;
the center lines of the plurality of sleeves are vertically coplanar with the center line of the guide rail, and the horizontal parallelism tolerance between the center lines of the plurality of sleeves and between the center line of the sleeve and the center line of the guide rail is less than 1 mm.
2. The device for controlling the accuracy of the embedded components of the push-pull device of the nuclear power plant as claimed in claim 1, wherein the detachable adjusting support is formed by welding angle steel and turnbuckle bolts.
3. The device for controlling the precision of the embedded component of the push-pull device of the nuclear power plant as claimed in claim 1, wherein a wedge-shaped limiting block can be arranged in the guide rail to fix the position of the push-pull device.
4. The method for installing the precision control device of the embedded component of the push-pull device of the nuclear power plant as claimed in claim 1, wherein the embedded component is located in a concrete base material, and the method comprises the following steps:
step 1: prefabricating an embedded sleeve, a detachable adjusting support and an embedded plate in a factory;
step 2: installing wall reinforcing steel bars and slab reinforcing steel bars on site, reserving holes needed for installing embedded sleeves, and installing the embedded sleeves and the embedded slabs;
and step 3: installing a concrete wall and plate template, and pouring concrete to obtain a cast-in-place concrete wall plate structure;
and 4, step 4: and welding the guide rail and the guide rail backing plate, and connecting the guide rail backing plate with the embedded plate through bolts.
5. The method of claim 4, wherein the step of installing includes factory manufacturing and assembly of the fastener inserts, and field installation and adjustment.
6. The method for installing the precision control device of the embedded component of the push-pull device of the nuclear power plant as claimed in claim 4, wherein the interface relationship between the embedded component and the reinforcing steel bars and other embedded items is determined in advance.
7. The installation method of the precision control device for the embedded component of the push-pull device of the nuclear power plant as claimed in claim 4, wherein the detachable adjusting support is removed before the embedded component is inserted into the hole reserved in the steel bar, and the detachable adjusting support is recovered after the embedded component is inserted into the hole reserved in the steel bar.
8. The method for installing the precision control device of the embedded component of the push-pull device of the nuclear power plant as claimed in claim 4, wherein the installation of the guide rail is performed after the embedded sleeve, the embedded plate and the concrete structure of the wall plate are installed.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201510990702.3A CN105609148B (en) | 2015-12-24 | 2015-12-24 | Device for precision control of embedded assembly of push-pull device of nuclear power plant and installation method |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201510990702.3A CN105609148B (en) | 2015-12-24 | 2015-12-24 | Device for precision control of embedded assembly of push-pull device of nuclear power plant and installation method |
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| CN105609148A CN105609148A (en) | 2016-05-25 |
| CN105609148B true CN105609148B (en) | 2020-02-07 |
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| CN105931681B (en) * | 2016-06-08 | 2019-03-01 | 中国核工业二三建设有限公司 | The installation tool and installation method of high temperature air-cooled pile pressure container built-in fitting |
| CN106223708A (en) * | 2016-08-31 | 2016-12-14 | 山东电力建设第工程公司 | Scheme had bad luck by a kind of inner steel cylinder of chimney barrel sheet material |
| CN107285230B (en) * | 2017-08-10 | 2019-10-25 | 中国十七冶集团有限公司 | The installation method of RH refining furnace hydraulic lifting guide rail |
| CN107795752B (en) * | 2017-09-19 | 2021-07-16 | 中国核电工程有限公司 | Transverse limiting structure and transverse limiting method for water supply pipeline of nuclear power station |
| CN111354482B (en) * | 2019-12-27 | 2022-04-15 | 中国核动力研究设计院 | Reactor core instrument assembly with reusable packing ring |
| CN113096836B (en) * | 2021-03-30 | 2022-03-01 | 陕西卫峰核电子有限公司 | Neutron detection system and installation method thereof |
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| FR2607309B1 (en) * | 1986-11-26 | 1989-04-28 | Framatome Sa | CONDUIT FOR SUPPORTING AND POSITIONING MEASURING DEVICES IN THE HEART OF A NUCLEAR REACTOR |
| JP5535100B2 (en) * | 2011-02-03 | 2014-07-02 | 三菱電機株式会社 | Out-of-core nuclear instrumentation |
| CN202601222U (en) * | 2012-06-13 | 2012-12-12 | 中国核动力研究设计院 | Neutron fluence rate detector positioning structure of ex-reactor nuclear instrumentation system |
| JP6112786B2 (en) * | 2012-06-15 | 2017-04-12 | 三菱電機株式会社 | In-reactor neutron flux detector position detector |
| CN104179794B (en) * | 2013-05-24 | 2018-09-07 | 中广核工程有限公司 | The attachment device and its installation method of nuclear power plant's out-of-core neutron flux measurement device |
| CN204254890U (en) * | 2014-11-03 | 2015-04-08 | 青岛经济技术开发区海尔热水器有限公司 | Inner container fixing structure of double-inner container water heater |
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: Shanghai Nuclear Engineering Research & Design Institute |
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Effective date of registration: 20210113 Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Patentee after: CHINA NUCLEAR INDUSTRY 23 CONSTRUCTION Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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