CN108922637A - A kind of nuclear power station-service control rod drive mechanism - Google Patents
A kind of nuclear power station-service control rod drive mechanism Download PDFInfo
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- CN108922637A CN108922637A CN201810823379.4A CN201810823379A CN108922637A CN 108922637 A CN108922637 A CN 108922637A CN 201810823379 A CN201810823379 A CN 201810823379A CN 108922637 A CN108922637 A CN 108922637A
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- control rod
- drive mechanism
- rod drive
- nuclear power
- power station
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- 230000007246 mechanism Effects 0.000 title claims abstract description 41
- 239000000523 sample Substances 0.000 claims abstract description 19
- 238000012544 monitoring process Methods 0.000 claims abstract description 4
- 230000007704 transition Effects 0.000 claims description 8
- 238000005259 measurement Methods 0.000 claims description 6
- 239000000463 material Substances 0.000 claims description 5
- 230000002528 anti-freeze Effects 0.000 claims description 4
- 238000001514 detection method Methods 0.000 claims description 4
- 238000005516 engineering process Methods 0.000 claims description 4
- 229910000831 Steel Inorganic materials 0.000 claims description 3
- 229910000963 austenitic stainless steel Inorganic materials 0.000 claims description 3
- 238000004519 manufacturing process Methods 0.000 claims description 3
- 230000011218 segmentation Effects 0.000 claims description 3
- 239000010959 steel Substances 0.000 claims description 3
- 229910000734 martensite Inorganic materials 0.000 claims description 2
- 229910001220 stainless steel Inorganic materials 0.000 claims description 2
- 239000010935 stainless steel Substances 0.000 claims description 2
- 238000010276 construction Methods 0.000 abstract description 4
- 238000006243 chemical reaction Methods 0.000 description 7
- 230000003139 buffering effect Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 238000004804 winding Methods 0.000 description 4
- 238000013461 design Methods 0.000 description 3
- 238000003466 welding Methods 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 230000001737 promoting effect Effects 0.000 description 2
- 210000003781 tooth socket Anatomy 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 208000035217 Ring chromosome 1 syndrome Diseases 0.000 description 1
- 208000032825 Ring chromosome 2 syndrome Diseases 0.000 description 1
- 208000032826 Ring chromosome 3 syndrome Diseases 0.000 description 1
- 230000009471 action Effects 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 229910052793 cadmium Inorganic materials 0.000 description 1
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 description 1
- 210000000078 claw Anatomy 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 229910052738 indium Inorganic materials 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- WABPQHHGFIMREM-UHFFFAOYSA-N lead(0) Chemical compound [Pb] WABPQHHGFIMREM-UHFFFAOYSA-N 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 230000005415 magnetization Effects 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 229910001105 martensitic stainless steel Inorganic materials 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 238000010008 shearing Methods 0.000 description 1
- 239000000758 substrate Substances 0.000 description 1
- 238000009423 ventilation Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/12—Means for moving control elements to desired position
- G21C7/14—Mechanical drive arrangements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/12—Means for moving control elements to desired position
- G21C7/16—Hydraulic or pneumatic drive
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The present invention provides a kind of nuclear power station-service control rod drive mechanism comprising：The pressure-resistant shell component of integral structure；The stick location probe on pressure-resistant shell component is installed on using variable transformer structure；The tube socket for using flange arrangement to be connected with pressure-resistant shell component；The high temperature coil block being connected with stick location probe lower end；Actuating arm assembly is passed through from hook component, and the lower end of actuating arm assembly is connected with the starframe of control rod；Waterpower ring cavity buffer unit is set in control rod drive mechanism.Control rod drive mechanism, physical location that is easy to disassemble and continuously can accurately monitoring control rod；Top pile structure is simplified, construction cost is reduced；Control rod ejection accident can be prevented by improving driving rod structure, improve driving mechanism traveling comfort and safety；Equipment safety coefficient is promoted using high temperature resistant coil.
Description
Technical field
The present invention relates to nuclear power generating equipment technical field more particularly to a kind of nuclear power station-service control rod drive mechanism.
Background technique
So-called nuclear power control rod is usually to be easy to absorb made of the material of neutron boron and cadmium etc..Nuclear reaction pressure vessel
There is a set of mechanical device can be with manipulation and control stick outside.When control rod is fully inserted into reaction center, a large amount of neutrons can be absorbed, with resistance
The only progress of fission chain reaction.If control rod is extracted a bit, reactor begins to operate, and the speed of chain reaction reaches
Certain stationary value；If it is desired to increasing the energy of reactor release, control rod need to only be extracted out again a bit, it is absorbed in this way in
Son is reduced, and has more neutrons to participate in fission reaction.The progress for stopping chain reaction, control rod is fully inserted into nuclear reaction
The heart sponges most of neutron.In nuclear reaction control process, the driving mechanism of control rod is played a crucial role.
Widely used magnetic force hoisting type control rod drive mechanism relies on M310 unit to be fitted mostly in nuclear power plant at present
Answering property Curve guide impeller.Pneumatic shell mostly uses multisection type " Ω " welding structure；Mounting means is then to be threadedly coupled to be welded with to connect；It mentions
It rises magnetic circuit buffering and relies primarily on 3 buffer substrate tablets；The heatproof of coil needs forced ventilation is cooling to maintain length at 220 DEG C or so
Phase operation；Rod position measuring device uses 5 or 6 Gray code formulas（Photoelectric encoder）Structure, Measurement Resolution is in ± 8 steps（About
127mm）.
Summary of the invention
Technical problem to be solved by the present invention lies in provide a kind of nuclear power station-service control rod drive mechanism, solve existing
The problem of control rod drive mechanism is not easy to disassemble, and heatproof is lower and easy generation control rod ejection accident.
In order to solve the above technical problem, the present invention provides a kind of nuclear power station-service control rod drive mechanism, may include：
The pressure-resistant shell component of integral structure；
The stick location probe being installed on the pressure-resistant shell component, the stick location probe are connected in real time using variable transformer structure
The physical location of continuous accurate monitoring control rod；
The tube socket for using flange arrangement to be connected with the pressure-resistant shell component；
The high temperature coil block being connected with the stick location probe lower end；
Actuating arm assembly is passed through from the hook component being installed in the pressure-resistant shell component hook room, the actuating arm assembly
Lower end is connected with the starframe of control rod；
Waterpower ring cavity buffer unit is set in the control rod drive mechanism.
In an alternate embodiment of the invention, blind-hole type stroke casing, transition segment and hook room are set in the pressure-resistant shell component.
In an alternate embodiment of the invention, the pressure-resistant shell component is welded using segmentation butt weld technologies for steel.
In an alternate embodiment of the invention, the blind-hole type stroke casing and transition segment select austenitic stainless steel material system
Make, martensite stainless steel material production is selected in the hook room.
In an alternate embodiment of the invention, seal with double-cone pad is set between the pressure-resistant shell component and the tube socket.
In an alternate embodiment of the invention, it is set on the tube socket and draws leakage device, leak detection dress is set between the seal with double-cone pad
It sets.
In an alternate embodiment of the invention, the stick location probe winding mode is that primary coil and secondary coil are wound respectively,
For the stick location probe in the measurement to control rod position, maximum error of measuring is+3% ~ -3%.
In an alternate embodiment of the invention, shaking of the necking down structure of the hook component to limit the actuating arm assembly.
In an alternate embodiment of the invention, the waterpower ring cavity, which is located at, is promoted between magnet and lift armature, the waterpower ring cavity
Inside set promotion spring.
In an alternate embodiment of the invention, kept apart between promotion magnet and the lift armature using antifreeze plate.
In an alternate embodiment of the invention, the coil heatproof upper limit value of the high temperature coil block is 350 DEG C.
In an alternate embodiment of the invention, the high temperature coil block includes three groups of high temperature resistant coils.
In an alternate embodiment of the invention, valving is set in the actuating arm assembly, it is upper when drive rod moves to reduce
Lower pressure difference.
In an alternate embodiment of the invention, the nuclear power station-service control rod drive mechanism is mounted on nuclear reactor pressure container top cover
Tube socket on.
In summary, the beneficial effect of the embodiment of the present invention is：Control rod drive mechanism of the invention, it is easy to disassemble and
It continuously can accurately monitor the physical location of control rod；Top pile structure is simplified, construction cost is reduced；Improve driving rod structure
It can prevent control rod ejection accident, improve driving mechanism traveling comfort and safety；It is not only simplified using high temperature resistant coil
System design is also promoted equipment safety coefficient.
Detailed description of the invention
In order to more clearly explain the embodiment of the invention or the technical proposal in the existing technology, to embodiment or will show below
There is attached drawing needed in technical description to be briefly described, it should be apparent that, the accompanying drawings in the following description is only this
Some embodiments of invention for those of ordinary skill in the art without creative efforts, can be with
It obtains other drawings based on these drawings.
Fig. 1 is a kind of assembling schematic diagram of one embodiment of nuclear power station-service control rod drive mechanism of the present invention.
Fig. 2 is pressure-resistant component assembling signal in a kind of one embodiment of nuclear power station-service control rod drive mechanism of the present invention
Figure.
Fig. 3 is pressure-resistant component and CRDM in a kind of one embodiment of nuclear power station-service control rod drive mechanism of the present invention（Even
Bar controls mechanical device）Tube socket connection schematic diagram.
Fig. 4 is stick location probe structural representation in a kind of one embodiment of nuclear power station-service control rod drive mechanism of the present invention
Figure.
Fig. 5 is hook component necking down signal in a kind of one embodiment of nuclear power station-service control rod drive mechanism of the present invention
Figure.
Fig. 6 is waterpower ring cavity schematic diagram in a kind of one embodiment of nuclear power station-service control rod drive mechanism of the present invention.
Fig. 7 is a kind of one embodiment high temperature coil block signal of nuclear power station-service control rod drive mechanism of the present invention
Figure.
It is as follows that corresponding note is identified in each figure of following embodiment：
Fig. 2：31, end socket 32, stroke casing 33, transition segment 34, hook room
Fig. 3：3, pressure-resistant shell component 81, bolt 82, nut 83, flange 84, seal with double-cone pad 9, CRDM tube socket 91, draw leakage
Device
Fig. 4：11, primary coil lead-out wire（Inlet side）12, primary coil 13, inner cylinder 14, secondary coil 15, secondary coil
Lead-out wire（Outlet）16, primary coil lead-out wire（Outlet）17, secondary coil lead-out wire（Inlet side）
Fig. 5：111, magnetic pole 72, quill 41, drive rod 74, adjustment ring 75, support ring are promoted
Fig. 6：111, it promotes magnetic pole 112, promote spring 113, waterpower ring cavity 114, antifreeze plate 115, lift armature
Fig. 7：601, lead wire 602, magnetic yoke disk -1-1 603, promotion coil 604, magnetic yoke disk -2-1 605, moving coil
606, magnetic yoke disk -2-2 607, magnetic yoke disk -3-1 608, hold-in winding
609, magnetic yoke disk -3-2 610, magnetic yoke bushing -4 611, magnet yoke ring -3 612, magnetic yoke bushing -3 613, magnet yoke ring -2
614, magnetic yoke bushing -2 615, magnetic yoke disk -1-2 616, magnet yoke ring -1 617, magnetic yoke bushing -1.
Specific embodiment
The explanation of following embodiment be with reference to attached drawing, can be to the specific embodiment implemented to the example present invention.
The embodiment of the present invention provides a kind of nuclear power station-service control rod drive mechanism, main as shown in the installation diagram of Fig. 1
By being constituted with lower component：
Stick location probe 1, outer sleeve 2, pressure-resistant shell component 3, actuating arm assembly 4, threaded connector 5, coil block 6, hook group
Part 7, double end stud connecting piece 8, CRDM tube socket 9 and auxiliary scram spring 10.
Wherein, stick location probe 1 is installed on the stroke casing of pressure-resistant shell component 3, the lower end of stick location probe 1 and coil
Component 6 is connected, and the magnetic yoke bushing of coil block 6 supports entire stick location probe 1；2 sets of the outer sleeve outsides in outer sleeve 2,
The lower end of outer sleeve 2 is connected by screw thread with the magnetic yoke disk of coil block 6；Hook component 7 is mounted on the hook of pressure-resistant shell component 3
Interior, actuating arm assembly 4 are passed through from hook component 7, and the lower end of actuating arm assembly 4 is by disconnecting head and control rod（Non- standard）
Starframe be connected；Auxiliary scram spring 10 is installed on the inside of CRDM tube socket 9, and the upper end of auxiliary scram spring 10 is placed in CRDM
It on the interior step surface of tube socket 9, is limited by the support ring of 7 lower end of hook component, the lower end of auxiliary scram spring 10 is then sat
Fall in the guide cylinder upper surface of control rod.
Further, as shown in connection with fig. 2, pressure-resistant shell component 3 is structure as a whole inner hollow, and the biggish one end of outer diameter is hook
Room 34, the lesser one end end of outer diameter are end socket 31, are successively arranged stroke casing 32 from 31 end of end socket toward 34 end of hook room（Stick position
Detector 1 is just mounted on the trip casing 32）, transition segment 33 is set between stroke casing 32 and hook room 34.The pneumatic shell
Component 3 eliminates end plug and gas vent, then uses blind-hole type row compared with the pneumatic shell in existing control rod drive mechanism
Journey casing 32 eliminates all " Ω " weld seams, and welding is realized using segmentation butt weld technologies for steel.In the present embodiment, hook
Room 34 uses martensitic stain less steel, stroke casing 32, transition segment 33 and the connecting flange between them（It does not mark）Then use
Austenitic stainless steel, because the butt weld between this trip casing 32, transition rings 33 and hook room 34 is dissimilar metal pair
Welding seam；Which adds the security reliabilities of pressure-resistant shell component 3.
Further, as shown in connection with fig. 3, flanged joint is used between pressure-resistant shell component 3 and CRDM tube socket 9, it is double using multiple groups
Header stud connector 8 is locked, and both can guarantee that its leakproofness easy to disassemble can also overhaul in this way.Wherein, studs connects
Part 8 comes to carry out screw-threaded coupling to flange 83 and CRDM tube socket 9 by bolt 81, nut 82, in pressure-resistant shell component 3 and CRDM tube socket 9
Between be lined with seal with double-cone pad 84, by the way of dual-seal, this further enhances leakproofness.In seal with double-cone pad 84
Between also add leakage detection apparatus（It does not mark）Once inner ring leakage occurs, leakage detection apparatus can collect leakage information to maintenance personal,
Also embedded with drawing at leakage device 91 to seal with double-cone pad 84 on CRDM tube socket 9, drawing leakage device 91 can be in occurring when leakage, by leakage
It draws, to guarantee that coolant liquid will not leak outside, sealing reliability is effectively ensured.
Further, the winding mode of stick location probe 1 as shown in Figure 4, utilization is that variable transformer linear measurement is former
Reason is totally different from the differential transformer principle of the prior art to measure.The stick location probe 1 is only by 12 He of primary coil
Secondary coil 14 is wound in respectively on inner cylinder 13, compared with the winding mode of the prior art, has both reduced connection joint quantity
To simplify control system, continuous measurement monitoring stick position can also be achieved, and the worst error of measurement is controlled ± 3%
In range.
Further, as shown in figure 5, the both ends of hook component 7 of the invention are all made of necking down structure, can effectively guarantee to drive
Stability of the lever 41 during being promoted and underthrust, the shaking of drive rod 41 caused by avoiding fit clearance excessive, so that
Obtaining control rod can adapt to the operating condition of all kinds of complexity.In the present embodiment, uniform tooth socket, hook are provided in the upper section of drive rod 41
Claw assembly 7 swings in or shows the tooth socket of drive rod 41 under the control of 6 power on/off of coil block, to realize to group of drive rods
Promotion, underthrust and the scram movement of part 4.Of course for security consideration, it is necessary to quill 72 be arranged outside drive rod 41, in casing
Setting adjusts ring 747 between axis 72 and support ring 75, the screw thread between quill 727 and support ring 757 can be made to carry out sufficiently pre-
Tightly, to reduce the shearing force sold in operation.
Further, as shown in fig. 6, buffering chip architecture in the prior art is cancelled, magnet 111 and lift armature are being promoted
Waterpower ring cavity 113 is added between 115, setting promotes spring in waterpower ring cavity 113, is promoting magnet 111 and lift armature 115
Contact surface between separated with antifreeze plate 114, avoid contacting firmly.Such structure is opposite compared with existing buffering chip architecture
Simply, and when promoting magnet 111 and lift armature 115 and being attracted, using in waterpower ring cavity 113 spring and hydraulic pressure it is common
It acts on to play better buffering effect, reduces the impact force promoted between magnet 111 and lift armature 115, used with being promoted
Service life simultaneously reduces spoilage.
Further, as shown in fig. 7, the coil block 6 of control rod drive mechanism of the present invention uses high temperature resistant coil, coil can
Resistance to maximum temperature is 350 DEG C.And three groups of coils are used, issue action command respectively to it by operating indoor control cabinet,
Three groups of coils then carry out power on/off according to pre-set program, and magnetic pole and armature are corresponded in hook component 7 to control
Magnetization, to realize the promotion of control rod, underthrust or power-off scram movement.Equipment itself is not only increased using high temperature resistant coil
Safety coefficient, while eliminating forced convertion equipment, do not need to carry out Cooling Design, simplify system and heap roof construction.
Further, it is provided with valving in actuating arm assembly 4, the pressure difference up and down when drive rod movement can be reduced, avoided
Control rod ejection accident occurs.
To sum up, driving mechanism of the invention is mounted on nuclear reactor pressure container top cover control rod drive mechanism tube socket
On, realized by control instruction control rod in reactor core is promoted, the operation such as underthrust, scram, to adjust reactor fortune
Row power makes reactor shutdown.
By above description it is found that the beneficial effects of the present invention are：Control rod drive mechanism of the invention, it is easy to disassemble
And it continuously can accurately monitor the physical location of control rod；Top pile structure is simplified, construction cost is being reduced；Improve drive rod
Structure can prevent control rod ejection accident, improve driving mechanism traveling comfort and safety；It is both simple using high temperature resistant coil
Having changed system design is also promoted equipment safety coefficient.
The above disclosure is only the preferred embodiments of the present invention, cannot limit the right model of the present invention with this certainly
It encloses, therefore equivalent changes made in accordance with the claims of the present invention, is still within the scope of the present invention.
Claims (9)
1. a kind of nuclear power station-service control rod drive mechanism, which is characterized in that including：
The pressure-resistant shell component of integral structure；
The stick location probe being installed on the pressure-resistant shell component, the stick location probe are connected in real time using variable transformer structure
The physical location of continuous accurate monitoring control rod；
The tube socket for using flange arrangement to be connected with the pressure-resistant shell component；
The high temperature coil block being connected with the stick location probe lower end；
Actuating arm assembly is passed through from the hook component being installed in the pressure-resistant shell component hook room, the actuating arm assembly
Lower end is connected with the starframe of control rod；
Waterpower ring cavity buffer unit is set in the control rod drive mechanism.
2. nuclear power station-service control rod drive mechanism according to claim 1, which is characterized in that set in the pressure resistance shell component
Blind-hole type stroke casing, transition segment and hook room.
3. nuclear power station-service control rod drive mechanism according to claim 1, which is characterized in that the pressure resistance shell component uses
Segmentation butt weld technologies for steel is welded；The blind-hole type stroke casing and transition segment select austenitic stainless steel material production,
Martensite stainless steel material production is selected in the hook room.
4. nuclear power station-service control rod drive mechanism according to claim 1, which is characterized in that the pressure resistance shell component and institute
It states and sets seal with double-cone pad between tube socket.
5. nuclear power station-service control rod drive mechanism according to claim 4, which is characterized in that set on the tube socket and draw leakage
Device sets leakage detection apparatus between the seal with double-cone pad.
6. nuclear power station-service control rod drive mechanism according to claim 1, which is characterized in that the stick location probe coiling
Mode is that primary coil and secondary coil are wound respectively, and the stick location probe in the measurement to control rod position, survey by maximum
Measuring error is+3% ~ -3%.
7. nuclear power station-service control rod drive mechanism according to claim 1, which is characterized in that the waterpower ring cavity, which is located at, to be mentioned
It rises between magnet and lift armature, sets promotion spring in the waterpower ring cavity；It is described
It is promoted and is kept apart between magnet and lift armature using antifreeze plate.
8. nuclear power station-service control rod drive mechanism according to claim 7, which is characterized in that the high temperature coil block packet
Containing three groups of high temperature resistant coils.
9. nuclear power station-service control rod drive mechanism according to claim 1, which is characterized in that set in the actuating arm assembly
Valving, to reduce the pressure difference up and down when drive rod movement；It is anti-that the nuclear power station-service control rod drive mechanism is mounted on core
On the tube socket for answering core pressure vessel top cover.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810823379.4A CN108922637A (en) | 2018-07-25 | 2018-07-25 | A kind of nuclear power station-service control rod drive mechanism |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810823379.4A CN108922637A (en) | 2018-07-25 | 2018-07-25 | A kind of nuclear power station-service control rod drive mechanism |
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| CN108922637A true CN108922637A (en) | 2018-11-30 |
Family
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| CN201810823379.4A Pending CN108922637A (en) | 2018-07-25 | 2018-07-25 | A kind of nuclear power station-service control rod drive mechanism |
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Citations (22)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CH623158A5 (en) * | 1976-07-26 | 1981-05-15 | Babcock & Wilcox Co | |
| US4863673A (en) * | 1988-08-26 | 1989-09-05 | General Electric Company | Check valve test method for control rod drive |
| FR2813388A1 (en) * | 2000-08-31 | 2002-03-01 | Framatome Sa | Nuclear reactor guide tube bore diameter monitoring apparatus comprises use of feeler with semi-cylindrical fixed and moving sections |
| CN1442863A (en) * | 2002-03-29 | 2003-09-17 | 清华大学 | Nuclear reactor control rod hydraulic driving system |
| CN101178946A (en) * | 2007-12-11 | 2008-05-14 | 中国核动力研究设计院 | Stepwise magnetic force hoisting type reactor control rod driving mechanism |
| CN101510452A (en) * | 2009-03-11 | 2009-08-19 | 哈尔滨工程大学 | Continuous mobile waterpower drive device of nuclear reactor control rod |
| CN201306465Y (en) * | 2008-10-30 | 2009-09-09 | 大连大高阀门有限公司 | Up-loading ball valve of handling system for high temperature gas cooled reactor fuel at first nuclear level. |
| US20090252272A1 (en) * | 2008-01-09 | 2009-10-08 | Analysis And Measurement Services Corporation | Advanced Digital Control Rod Position Indication System with Rod Drop Monitoring for Nuclear Power Plants |
| CN102226484A (en) * | 2011-04-11 | 2011-10-26 | 江苏大学 | On-line monitoring device for seal leakage at valve stem of nuclear-grade valve |
| US20120148006A1 (en) * | 2010-12-14 | 2012-06-14 | Westinghouse Electric Company Llc | Nuclear reactor control rod drive mechanism |
| CN103886923A (en) * | 2013-12-04 | 2014-06-25 | 中科华核电技术研究院有限公司 | System and method for linearly measuring position of control rod |
| CN103971800A (en) * | 2014-05-26 | 2014-08-06 | 中科华核电技术研究院有限公司 | Winding wire of high-temperature-resistance electromagnetic coil and manufacturing method of winding wire |
| CN104616706A (en) * | 2015-02-05 | 2015-05-13 | 喻杰 | Integrated pressure-resistant shell assembly |
| CN105761765A (en) * | 2016-03-30 | 2016-07-13 | 中国核动力研究设计院 | Star-shaped buffering structure achieving reactor control rod buffering function and method thereof |
| CN105788669A (en) * | 2016-05-06 | 2016-07-20 | 上海核工程研究设计院 | Built-in type control bar driving mechanism |
| WO2016115821A1 (en) * | 2015-01-23 | 2016-07-28 | 李泽文 | Nickel-based alloy pressure-resistant shell and implementation method thereof |
| CN106098110A (en) * | 2016-06-16 | 2016-11-09 | 中国核动力研究设计院 | Reactor control rod drives line buffer structure |
| CN106205748A (en) * | 2016-08-31 | 2016-12-07 | 四川华都核设备制造有限公司 | Reactor control rod driving mechanism |
| CN106531238A (en) * | 2016-12-15 | 2017-03-22 | 中国核动力研究设计院 | Main pump pressure vessel provided with double layers of casings |
| CN107767970A (en) * | 2017-10-20 | 2018-03-06 | 中国核动力研究设计院 | A kind of long-life high-temperature resistant magnetic force hoisting type reactor control rod driving mechanism |
| CN107945890A (en) * | 2017-12-15 | 2018-04-20 | 中广核工程有限公司 | Nuclear power station reactor control stick driving mechanism |
| CN208873481U (en) * | 2018-07-25 | 2019-05-17 | 中广核研究院有限公司 | A kind of nuclear power station-service control rod drive mechanism |
-
2018
- 2018-07-25 CN CN201810823379.4A patent/CN108922637A/en active Pending
Patent Citations (22)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CH623158A5 (en) * | 1976-07-26 | 1981-05-15 | Babcock & Wilcox Co | |
| US4863673A (en) * | 1988-08-26 | 1989-09-05 | General Electric Company | Check valve test method for control rod drive |
| FR2813388A1 (en) * | 2000-08-31 | 2002-03-01 | Framatome Sa | Nuclear reactor guide tube bore diameter monitoring apparatus comprises use of feeler with semi-cylindrical fixed and moving sections |
| CN1442863A (en) * | 2002-03-29 | 2003-09-17 | 清华大学 | Nuclear reactor control rod hydraulic driving system |
| CN101178946A (en) * | 2007-12-11 | 2008-05-14 | 中国核动力研究设计院 | Stepwise magnetic force hoisting type reactor control rod driving mechanism |
| US20090252272A1 (en) * | 2008-01-09 | 2009-10-08 | Analysis And Measurement Services Corporation | Advanced Digital Control Rod Position Indication System with Rod Drop Monitoring for Nuclear Power Plants |
| CN201306465Y (en) * | 2008-10-30 | 2009-09-09 | 大连大高阀门有限公司 | Up-loading ball valve of handling system for high temperature gas cooled reactor fuel at first nuclear level. |
| CN101510452A (en) * | 2009-03-11 | 2009-08-19 | 哈尔滨工程大学 | Continuous mobile waterpower drive device of nuclear reactor control rod |
| US20120148006A1 (en) * | 2010-12-14 | 2012-06-14 | Westinghouse Electric Company Llc | Nuclear reactor control rod drive mechanism |
| CN102226484A (en) * | 2011-04-11 | 2011-10-26 | 江苏大学 | On-line monitoring device for seal leakage at valve stem of nuclear-grade valve |
| CN103886923A (en) * | 2013-12-04 | 2014-06-25 | 中科华核电技术研究院有限公司 | System and method for linearly measuring position of control rod |
| CN103971800A (en) * | 2014-05-26 | 2014-08-06 | 中科华核电技术研究院有限公司 | Winding wire of high-temperature-resistance electromagnetic coil and manufacturing method of winding wire |
| WO2016115821A1 (en) * | 2015-01-23 | 2016-07-28 | 李泽文 | Nickel-based alloy pressure-resistant shell and implementation method thereof |
| CN104616706A (en) * | 2015-02-05 | 2015-05-13 | 喻杰 | Integrated pressure-resistant shell assembly |
| CN105761765A (en) * | 2016-03-30 | 2016-07-13 | 中国核动力研究设计院 | Star-shaped buffering structure achieving reactor control rod buffering function and method thereof |
| CN105788669A (en) * | 2016-05-06 | 2016-07-20 | 上海核工程研究设计院 | Built-in type control bar driving mechanism |
| CN106098110A (en) * | 2016-06-16 | 2016-11-09 | 中国核动力研究设计院 | Reactor control rod drives line buffer structure |
| CN106205748A (en) * | 2016-08-31 | 2016-12-07 | 四川华都核设备制造有限公司 | Reactor control rod driving mechanism |
| CN106531238A (en) * | 2016-12-15 | 2017-03-22 | 中国核动力研究设计院 | Main pump pressure vessel provided with double layers of casings |
| CN107767970A (en) * | 2017-10-20 | 2018-03-06 | 中国核动力研究设计院 | A kind of long-life high-temperature resistant magnetic force hoisting type reactor control rod driving mechanism |
| CN107945890A (en) * | 2017-12-15 | 2018-04-20 | 中广核工程有限公司 | Nuclear power station reactor control stick driving mechanism |
| CN208873481U (en) * | 2018-07-25 | 2019-05-17 | 中广核研究院有限公司 | A kind of nuclear power station-service control rod drive mechanism |
Non-Patent Citations (1)
| Title |
|---|
| 宋威等: "水力缓冲器缓冲特性研究", 原子能科学技术, vol. 47, no. 8, pages 1316 - 1321 * |
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| CN112361110A (en) * | 2020-09-27 | 2021-02-12 | 中核核电运行管理有限公司 | Connecting device and method for corrosion-resistant alloy bushing of leakage guide pipe of primary loop valve |
| WO2022121458A1 (en) * | 2020-12-11 | 2022-06-16 | 中广核研究院有限公司 | Control rod control device and reactor |
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