CN206619400U - A kind of nuclear power plant's CRDM antidetonation supporting system - Google Patents
A kind of nuclear power plant's CRDM antidetonation supporting system Download PDFInfo
- Publication number
- CN206619400U CN206619400U CN201720011875.0U CN201720011875U CN206619400U CN 206619400 U CN206619400 U CN 206619400U CN 201720011875 U CN201720011875 U CN 201720011875U CN 206619400 U CN206619400 U CN 206619400U
- Authority
- CN
- China
- Prior art keywords
- crdm
- antidetonation
- power plant
- nuclear power
- shroud
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Classifications
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
A kind of nuclear power plant's CRDM antidetonation supporting system of the utility model, it includes shroud, the Tiebar structure on the outside of antidetonation supporting structure framework, lattice structure, drive mechanism connecting plate, attachment structure and shroud on the inside of shroud.Nuclear power plant's CRDM antidetonation supporting system that the utility model is provided, the characteristics of system has convenient installation and removal, flexible and strong adaptability.During reloading, if rod position detection device or the yoke loop construction on CRDM need to be changed, it is only necessary to which the rod position detection device or yoke loop construction on single CRDM are hung out into replacing from the network respectively.Because the lattice structure integral rigidity in patent is larger, every group of CRDM so as to avoid the superposition of each CRDM displacement, and then can only reduce CRDM Root Stress in each self-corresponding grid bias internal.Meanwhile, under earthquake working condition, the impact load acted on CRDM also has a certain degree of reduction.
Description
Technical field
The utility model is related to nuclear power plant's nuclear reactor designs, and in particular to a kind of nuclear power plant's CRDM antidetonation
Supporting system.
Background technology
In pressurized-water reactor nuclear power plant, the drive of magnetic force hoisting type control rod is usually mounted with top cover of reactor pressure vessel (RVCH)
Motivation structure (CRDM).Because CRDM is to ensure that the controllable visual plant of reactor safety, it is acted under normal and accident conditions
Reliability be directly connected to the safe operation of whole nuclear power station.In order to provide enough enabling capabilities to elongated CRDM, carry
CRDM antidetonation supporting structures are generally arranged on high CRDM functional reliability, heap top.
In AP1000CRDM antidetonation support structure designs, CRDM antidetonations supporting system is main on integrated heap top component
Stick location probe (DRPI) plate composition at the top of antidetonation supporting structure, shroud component and CRDM.Antidetonation supporting structure carries for CRDM
For antidetonation constraint, it is located at the correct position of CRDM stroke housing, with the DRPI connecting plate groups on stroke housing
Into CRDM lateral supports.The supporting structure is connected with shroud component, and seismic (seismal is delivered to pressure vessel from drive mechanism
On top cover.
The antidetonation supporting structure disposed inboard of the system have between more DRPI plates, each DRPI plates exist it is certain between
There is also gap between gap, and DRPI plates and the supporting of CRDM antidetonations.In the case of being accumulated in gap larger position can be produced at the top of CRDM
Move, cause root to produce larger stress.Meanwhile, larger collision load can be also produced between DRPI plates under earthquake operating mode
Lotus.
Relevant design unit once used the design side that the DRPI plates that fritter is replaced with the big anti-seismic plate of monoblock are combined
The problem of formula is to reduce CRDM penetration pieces root and impact load.In this design, the overall position under earthquake operating mode at the top of CRDM
Move smaller, the collisionless load and impact load of anti-seismic plate and the quake-proof supporting structure on IHP is also smaller between DRPI plates.
But the design of this monoblock anti-seismic plate will greatly reduce the flexibility of CRDM replacings.
In a kind of patent " presurized water reactor CRDM tabular antidetonation ring " (application number:201220702271.8) in,
Utility model a kind of CRDM tabular antidetonation ring, the seismic support for CRDM.Needed to ensure to install, it is adjacent
Still there is larger gap between tabular antidetonation ring, the tabular antidetonation ring can not still solve the problems, such as the gap accumulation between each CRDM.
Utility model content
The utility model in view of the shortcomings of the prior art, proposes a kind of nuclear power plant's CRDM antidetonation supporting system
System.
Nuclear power plant's CRDM antidetonation supporting system include shroud, the antidetonation supporting structure framework on the inside of shroud,
Tiebar structure on the outside of lattice structure, drive mechanism connecting plate, attachment structure and shroud;Wherein, the drive mechanism connecting plate
Link into an integrated entity and constrained by lattice structure with drive mechanism;The lattice structure is connected with antidetonation supporting structure framework, is formed
Antidetonation constraint to CRDM;Described antidetonation supporting structure framework and attachment structure are arranged on the shroud and connected;It is described
The connection of Tiebar structure one end attachment structure, the other end is then fixed on concrete structure platform.
Preferably, the antidetonation supporting structure framework, shroud, attachment structure and Tiebar structure provide for the supporting of CRDM antidetonations
Support carrier.
Preferably, it is the grid of square or subquadrate inside the lattice structure.
Preferably, the drive mechanism connecting plate is square or subquadrate (opening chamfering etc.).
Preferably, each drive mechanism connecting plate is by the grid constraints.
Preferably, the concave polygon or convex polygon arranged on the inside of the antidetonation supporting structure framework for energy envelope drive mechanism
Shape.
Preferably, the lattice structure is arranged on the inside of antidetonation supporting structure framework, solid by connecting pin or attachment screw
It is scheduled on antidetonation supporting structure framework.
Preferably, the angle between the transverse slat and riser of grid is 90 degree;It is connected as between transverse slat and riser dismountable
Structure;Transverse slat and riser have neck to ensure the size and tolerance of transverse slat and stringer board;Lattice structure vertical direction has one
Fixed thickness is to adjust the influence of CRDM thermal deformation.
Preferably, each grid of lattice structure surrounds one piece of drive mechanism connecting plate;Four sides of grid and driving machine
Structure connecting plate outer side edges are away from equal.
Compared with prior art, the utility model has the advantages that:
1st, nuclear power plant's CRDM antidetonation supporting system that the utility model is provided, the system has peace installation and dismantling
The characteristics of unloading convenience, flexible and strong adaptability.During reloading, if rod position detection device or the yoke coil knot on CRDM need to be changed
Structure, it is only necessary to which the rod position detection device or yoke loop construction on single CRDM are hung out into replacing from the network respectively.Peace
During dress, due to the positioning action of each grid, the structure is also facilitated very much for CRDM installation.Because network is whole
Body is rigidly larger, every group of CRDM can only in each self-corresponding grid bias internal, so as to avoid the superposition of each CRDM displacement, and then
Reduce CRDM Root Stress.Meanwhile, under earthquake working condition, the impact load acted on CRDM also has a certain degree of
Reduce.
Brief description of the drawings
Nuclear power plant's CRDM antidetonation supporting system schematic diagram (1) that Fig. 1 provides for the utility model.
Nuclear power plant's CRDM antidetonation supporting system schematic diagram (2) that Fig. 2 provides for the utility model.
Fig. 3 is lattice structure schematic diagram.
Fig. 4 is lattice structure and antidetonation supporting structure framework connection diagram.
Fig. 5 is lattice structure schematic internal view.
Embodiment
To enable above-mentioned purpose of the present utility model, feature and advantage more obvious understandable, below in conjunction with the accompanying drawings and tool
Body embodiment is described in further detail to the utility model.
As illustrated, a kind of antidetonation supporting system for PWR nuclear power plant magnetic force hoisting type CRDM.
Antidetonation supporting structure framework 102 of the system on the inside of shroud 101, shroud, lattice structure 103, drive mechanism connect
Fishplate bar 104, attachment structure 105, the Tiebar structure 106 on the outside of shroud are constituted.
Shroud 101, attachment structure 105, Tiebar structure 106 in this patent provide support for the supporting of CRDM antidetonations and carried
Body.Shroud 101 is annular, and attachment structure 105 is fixed on shroud.And one end of Tiebar structure 106 then passes through bearing pin and company
Binding structure connected 105, the other end of Tiebar structure is fixed on Factory Concrete platform.
It is the grid of square or subquadrate, drive mechanism connecting plate 104 inside lattice structure 103 in this patent
Also it is square or subquadrate.Each drive mechanism connecting plate 104 is by a grid constraints.
Concave polygon or convex polygon that the inner side of antidetonation supporting structure framework 102 is arranged for energy envelope drive mechanism 110, outside
Side is circle.
Lattice structure 103 is arranged in the inner side of antidetonation supporting structure framework 102, is fixed by connecting pin or attachment screw 107.
Lattice structure 103 is made up of some pieces of Turbogrid plates 111.Folder between the transverse slat 108 and riser 109 of Turbogrid plates 111
Angle is 90 degree, and dismountable structure is connected as between transverse slat 108 and riser 109.There are neck, two on transverse slat 108 and riser 109
Individual neck pairing.Fluting matching method installs the size and tolerance that ensure that transverse slat and stringer board, contiguous block 112 and connection
The fixation that screw 113 is then used between Turbogrid plates 111.
Each square grid of lattice structure 103 surrounds one piece of drive mechanism connecting plate 104.Four sides of grid are with driving
The distance of the outer side edges of motivation structure connecting plate 104 is equal.
Compared with prior art, the present embodiment has the advantages that:
1st, nuclear power plant's CRDM antidetonation supporting system that the present embodiment is provided, the system has installation and removal
Conveniently, the characteristics of flexible and strong adaptability.During reloading, if rod position detection device or the yoke coil knot on CRDM need to be changed
Structure, it is only necessary to which the rod position detection device or yoke loop construction on single CRDM are hung out into replacing from the network respectively.Peace
During dress, due to the positioning action of each grid, the structure is also facilitated very much for CRDM installation.Because network is whole
Body is rigidly larger, every group of CRDM can only in each self-corresponding grid bias internal, so as to avoid the superposition of each CRDM displacement, and then
Reduce CRDM Root Stress.Meanwhile, under earthquake working condition, the impact load acted on CRDM also has a certain degree of
Reduce.
The embodiment of each in this specification is described by the way of progressive, and what each embodiment was stressed is and other
Between the difference of embodiment, each embodiment identical similar portion mutually referring to.For system disclosed in embodiment
For, due to corresponding to the method disclosed in Example, so description is fairly simple, related part is referring to method part illustration
.
Those skilled in the art can realize described function to each specific application using distinct methods, but
It is this realize it is not considered that beyond scope of the present utility model.
Obviously, those skilled in the art can be new without departing from this practicality to the various changes of utility model progress and modification
The spirit and scope of type.So, if these modifications and variations of the present utility model belong to the utility model claim and its
Within the scope of equivalent technologies, then the utility model is also intended to including these changes and modification.
Claims (9)
1. a kind of nuclear power plant's CRDM antidetonation supporting system, it is characterised in that including the antidetonation on the inside of shroud, shroud
Tiebar structure on the outside of supporting structure framework, lattice structure, drive mechanism connecting plate, attachment structure and shroud;Wherein, the grid
Lattice structure and the attachment structure are arranged on the shroud and connected, and the drive mechanism connecting plate is arranged on the shroud
It is interior.
2. nuclear power plant's CRDM antidetonation supporting system according to claim 1, it is characterised in that the antidetonation
Supporting structure framework, shroud, attachment structure and Tiebar structure provide support carrier for the supporting of CRDM antidetonations.
3. nuclear power plant's CRDM antidetonation supporting system according to claim 1, it is characterised in that the grid
Inside configuration is the grid of square.
4. nuclear power plant's CRDM antidetonation supporting system according to claim 1, it is characterised in that the driving
Mechanism connecting plate profile is square.
5. nuclear power plant's CRDM antidetonation supporting system according to claim 1, it is characterised in that each described
Drive mechanism connecting plate is by the grid constraints.
6. nuclear power plant's CRDM antidetonation supporting system according to claim 1, it is characterised in that the antidetonation
The concave polygon or convex polygon arranged on the inside of supporting structure framework for energy envelope drive mechanism.
7. nuclear power plant's CRDM antidetonation supporting system according to claim 1, it is characterised in that the grid
Structure is arranged on the inside of antidetonation supporting structure framework, is fixed on by connecting pin or attachment screw on antidetonation supporting structure framework.
8. nuclear power plant's CRDM antidetonation supporting system according to claim 1, it is characterised in that lattice structure
In be made up of the grid consistent with drive mechanism quantity, the angle between the transverse slat and riser of lattice structure is 90 degree;Transverse slat and
Dismountable structure is connected as between riser;The size and tolerance that transverse slat and riser have neck to ensure transverse slat and stringer board will
Ask;Lattice structure vertical direction has certain thickness with the influence for the thermal deformation for adjusting CRDM.
9. nuclear power plant's CRDM antidetonation supporting system according to claim 1, it is characterised in that lattice structure
Each grid surround one piece of drive mechanism connecting plate;Four sides of grid are with drive mechanism connecting plate outer side edges away from equal.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201720011875.0U CN206619400U (en) | 2017-01-05 | 2017-01-05 | A kind of nuclear power plant's CRDM antidetonation supporting system |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201720011875.0U CN206619400U (en) | 2017-01-05 | 2017-01-05 | A kind of nuclear power plant's CRDM antidetonation supporting system |
Publications (1)
Publication Number | Publication Date |
---|---|
CN206619400U true CN206619400U (en) | 2017-11-07 |
Family
ID=60229547
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201720011875.0U Active CN206619400U (en) | 2017-01-05 | 2017-01-05 | A kind of nuclear power plant's CRDM antidetonation supporting system |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN206619400U (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN106782690A (en) * | 2017-01-05 | 2017-05-31 | 上海核工程研究设计院 | A kind of nuclear power plant's CRDM antidetonation supporting system |
RU2724924C2 (en) * | 2018-01-15 | 2020-06-26 | Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" | Actuator of nuclear reactor control and protection system |
-
2017
- 2017-01-05 CN CN201720011875.0U patent/CN206619400U/en active Active
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN106782690A (en) * | 2017-01-05 | 2017-05-31 | 上海核工程研究设计院 | A kind of nuclear power plant's CRDM antidetonation supporting system |
RU2724924C2 (en) * | 2018-01-15 | 2020-06-26 | Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" | Actuator of nuclear reactor control and protection system |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN206619400U (en) | A kind of nuclear power plant's CRDM antidetonation supporting system | |
CN106782690A (en) | A kind of nuclear power plant's CRDM antidetonation supporting system | |
CN103871496A (en) | Integrated reactor roof structure for pressurized water reactor | |
CN104060830A (en) | Method for lifting and transporting large parts of underground nuclear power station | |
CN209052278U (en) | Suspender and beam shifting machine | |
CN102182259A (en) | Assembling method and device for assembled type anti-buckling envload support | |
WO2011144971A1 (en) | A bulkhead for an aerogenerator blade root | |
CN204594695U (en) | A kind of small-sized transverse axis wind mill performance testboard bay | |
US8670519B2 (en) | Nuclear fuel assembly hold down spring | |
CN211037768U (en) | Maintenance platform for aerial work in tower barrel of wind power plant | |
CN206568093U (en) | High-pressure self-sealing manhole tool specially for attaching and detaching | |
CN205869865U (en) | Laborsaving extraction element of cantilever pendulum rod formula | |
CN203026159U (en) | Integrated reactor roof structure of pressurized water reactor | |
CN209247537U (en) | The pipe tester of the more than enough root canal material of energy pressure testing simultaneously | |
CN207663807U (en) | A kind of auxiliary mounting tool of irradiation blockage | |
CN107134300B (en) | A kind of boom hoisting for Technologies of PWR Vessels cap assembly | |
CN209144908U (en) | A kind of shoveling equipment locking teeth device | |
CN106499590B (en) | A kind of offshore lifting method of ultra-compact two blade wind power generations unit | |
CN107902591A (en) | A kind of nuclear power plant shields door frame mounting tool | |
CN103998366B (en) | The shackle of slinging of nuclear reactor upper structure | |
CN203026151U (en) | Pressurized water reactor control rod driving mechanism plate-shaped buffer ring | |
CN208830833U (en) | A kind of safe fence net | |
CN208327249U (en) | A kind of nuclear power plant's shielding door frame mounting tool | |
CN203134394U (en) | Pull bar device for upper horizontal support of steam generator at nuclear power station | |
KR101147938B1 (en) | An apparatus for Pulling up Multiple Stud Tensioner |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
GR01 | Patent grant | ||
GR01 | Patent grant | ||
CP01 | Change in the name or title of a patent holder | ||
CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |