CN105788669A - Built-in type control bar driving mechanism - Google Patents
Built-in type control bar driving mechanism Download PDFInfo
- Publication number
- CN105788669A CN105788669A CN201610298040.8A CN201610298040A CN105788669A CN 105788669 A CN105788669 A CN 105788669A CN 201610298040 A CN201610298040 A CN 201610298040A CN 105788669 A CN105788669 A CN 105788669A
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- China
- Prior art keywords
- built
- crdm
- hook
- pawl
- magnetic pole
- Prior art date
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- Pending
Links
- 230000007246 mechanism Effects 0.000 title abstract description 12
- 230000001737 promoting effect Effects 0.000 claims description 3
- 230000008901 benefit Effects 0.000 abstract description 8
- 239000002826 coolant Substances 0.000 abstract description 8
- 210000000078 claw Anatomy 0.000 abstract 2
- 238000000034 method Methods 0.000 description 8
- 238000010276 construction Methods 0.000 description 5
- 238000007789 sealing Methods 0.000 description 5
- 238000003466 welding Methods 0.000 description 5
- 230000008859 change Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 230000004048 modification Effects 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000009471 action Effects 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 230000009467 reduction Effects 0.000 description 2
- 230000002787 reinforcement Effects 0.000 description 2
- 230000008439 repair process Effects 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 230000005540 biological transmission Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 230000011218 segmentation Effects 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
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention provides a built-in type control bar driving mechanism. The built-in type control bar driving mechanism comprises a pressure casing part, a magnetic yoke coil part, a hook claw part and a driving rod part, wherein the magnetic yoke coil part is sheathed at the exterior of the pressure casing part; the hook claw part is arranged in the pressure casing part; the driving rod part is arranged in the pressure casing part. The built-in type control bar driving mechanism has the advantage that the built-in type control bar driving mechanism is arranged in the pressure container of a reactor, is of an integrated magnetic yoke structure with small cross section, and is connected with a positioning flange by threads, so that the simple connection with the positioning flange is realized, a enough flow passage space is provided for coolants, and the requirements of compact structure, small size, enhanced natural circulation capability and the like of a nuclear reactor are met.
Description
Technical field
The present invention relates to the CRDM of nuclear power plant reactor, specifically the design of a kind of built-in CRDM.
Background technology
Command bundle rods for nuclear reactors driving mechanism is the safety equipment of reactor most critical, it is responsible for the starting of reactor, the critical function such as power adjustments and safe shutdown: according to the instruction of reactor control and protection system, C&P systems is driven to move up and down at heap in-core, keep C&P systems at command altitude, and release control rod assembly when power is off, make C&P systems quick insertion reactor core under gravity, thus completing the startup of reactor, power adjustments, keep power, the functions such as normal shutdown and breakdown, it is reactor capability control and the core system of reactor safety control.It is in the position in reactor by CRDM equipment to divide, has " built-in " and " external " two kinds of arrangements available.
Wherein, it is that CRDM is placed in outside reactor pressure vessel that external drives, as presurized water reactor CRDM magnetic force hoisting mechanism is positioned on pressure vessel lid, advanced boiling water reactor CRDM is positioned at pressure vessel bottom, accounts for the 1/3 of whole pile height.The disadvantage that external drives is transmission line length, increases reactor overall height and there is bullet rod hidden danger.
Summary of the invention
The present invention is directed to the deficiencies in the prior art, it is proposed to a kind of built-in CRDM.
Built-in CRDM includes:
Pressure-bearing case member；Described pressure-bearing case member, by being axially divided into three sections from top to bottom, is made up of rod stroke housing, hook housing and guide thimble；Adopt threaded between described rod stroke housing and described hook housing, adopt between described hook housing and described guide thimble and threaded；
Magnetic inversion line coil component；Described magnetic inversion line coil component is sleeved on outside described pressure-bearing case member；
Hook parts；Described hook parts are arranged in described pressure-bearing case member；And
Drive-rod part；Described drive-rod part is arranged on inside described pressure-bearing case member.
Preferably, described hook parts by promoting magnetic pole, pawl magnetic pole, pawl armature, determine pawl magnetic pole, determine pawl armature, hook and quill and form；Described lifting magnetic pole, pawl magnetic pole, pawl armature, determine pawl magnetic pole, determine pawl armature, hook is sleeved on described quill.
Preferably, described magnetic inversion line coil component is made up of a yoke assembly and three actuating coils.
Preferably, described yoke assembly is monoblock type cylindrical structure form.
Preferably, described hook housing adopts with locating flange and threadeds.
Compared with prior art, the method have the advantages that
1, built-in CRDM provided by the invention, it is positioned over inside reactor pressure vessel, there is little cross section integrated magnet yoke structure, adopt threaded with locating flange, both it had been connected simple with locating flange, enough flow channel space can be provided for coolant again, meet the requirements such as nuclear reactor is compacter, volume is little, natural-circulation capacity reinforcement.
2, built-in CRDM provided by the invention, is placed in CRDM in pressure vessel, shortens driving line.Thus reducing pile height；Avoid control rod ejection accident, enhance nuclear reactor safety.Therefore, built-in actuation techniques has greater advantage in integrated arrangement nuclear reactor.
3, built-in CRDM provided by the invention, operation principle is identical with the CRDM of external, but whole CRDM is placed in inside pressure vessel and works close to core region, to there is provided runner reasonable distribution flow for reactor coolant, therefore structural design to differ greatly with CRDM conventional at present:
1) due to inside and outside built-in CRDM equipment without pressure reduction, its external shell parts are no longer belong to primary Ioops pressure boundary, and original pressure-bearing shell designing requirement can be greatly reduced.
2) original external split yoke is owing to adopting box-structure, and sectional area is excessive, and this structure is placed on the resistance that can be greatly increased runner inside pressure vessel, it is necessary to adopt the magnetic yoke structure with more small bore.
3) adopt built-in CRDM, after its actuating coil is placed in coolant, the waterproof sealing of electric component need to be considered, adopt integrated sealing form to have simple in construction, the advantage that reliability is high.
4) in order to reduce CRDM and the contact area installing locating flange, it is effectively increased the runner perforated area installed on locating flange, driving mechanism is installed to adopt between locating flange with CRDM and is threadeded, it also avoid the welding residual stress adopting welding to cause and base deformation simultaneously, simple in construction, it is simple to change, keep in repair and storage.
Accompanying drawing explanation
Fig. 1 is the built-in CRDM schematic diagram meeting the preferred embodiment of the present invention.
Fig. 2 is the hook block diagram meeting the preferred embodiment of the present invention.
Fig. 3 is the magnetic inversion line coil component schematic diagram meeting the preferred embodiment of the present invention.
Fig. 4 is the magnetic inversion line coil component Section A-A schematic diagram meeting the preferred embodiment of the present invention
Detailed description of the invention
Understandable for enabling the above-mentioned purpose of the present invention, feature and advantage to become apparent from, below in conjunction with the drawings and specific embodiments, the present invention is further detailed explanation.
As shown in Figure 1, the built-in reactor control rod driving mechanism of the present invention is made up of rod stroke housing 1, drive-rod part 2, hook parts 3, magnetic inversion line coil component 4, hook housing 5 and guide thimble 7, and wherein rod stroke housing 1, hook housing 5 and guide thimble 7 constitute pressure-bearing case member.Whole mechanism is directly installed on the CRDM locating flange 6 of reactor pressure vessel by the screw thread of hook housing 5 lower end；Adopt threaded between rod stroke housing 1 and hook housing 5, adopt between hook housing 5 with guide thimble 7 and threaded；Outside the hook housing 5 that magnetic inversion line coil component 4 is sleeved on, the operation that the electromagnetic attraction of its generation is hook parts 3 provides power source；Hook parts 3, in the inside of hook housing 5, realize radially location by location nut；Drive-rod part 2 is through hook parts 3, and pressure-bearing case member provides the space moved up and down for drive-rod part 2；Guide housing is arranged at guide thimble 7 bottom, enters the internal offer guide effect of pressure-bearing case member for installing drive rod.
As in figure 2 it is shown, the hook parts of the present invention are the action components of driving mechanism, by promoting magnetic pole 8, pawl magnetic pole 9, quill 10, pawl armature 11, mobile hook 12, determine pawl magnetic pole 13, determine pawl armature 14 and fixing hook 15 forms.Promote magnetic pole 8 and be threadedly attached in the high order end of quill 10, and fix with holding screw；Pawl magnetic pole 9, pawl armature 11, determine pawl magnetic pole 13 and determine pawl armature 14 and be from left to right sleeved on successively on quill 10；The cannelure engagement of mobile hook 12 and drive-rod part 2, by promote magnetic pole 8 and the suction of pawl magnetic pole 9 put drive mobile hook rise or fall to promote or lower slotting drive-rod part 2；When mobile hook 12 is reorientated for next step action, fixing hook 15 keeps drive-rod part motionless.
As shown in Figure 3 and Figure 4, magnetic inversion line coil component of the present invention mainly by a yoke assembly 16, promote coil 17, pawl coil 19 and determine pawl coil 21 and form.1# locating ring and 2# locating ring are for limiting pawl coil 19 and determining the axial location of pawl coil 21；Housing 22 is welded in the two ends of yoke assembly 16, it is achieved the waterproof sealing of three actuating coils；For reducing the resistance that coolant is flowed by yoke profile, yoke adopts cylindrical structure form, leaves electric conduit passage simultaneously；Yoke assembly is monolithic construction, and the techniques such as segmentation welding can be adopted to ensure its complete seal.
Compared with prior art, the method have the advantages that
1, the built-in CRDM that the present embodiment provides, it is positioned over inside reactor pressure vessel, there is little cross section integrated magnet yoke structure, adopt threaded with locating flange, both it had been connected simple with locating flange, enough flow channel space can be provided for coolant again, meet the requirements such as nuclear reactor is compacter, volume is little, natural-circulation capacity reinforcement.
2, the built-in CRDM that the present embodiment provides, is placed in CRDM in pressure vessel, shortens driving line.Thus reducing pile height；Avoid control rod ejection accident, enhance nuclear reactor safety.Therefore, built-in actuation techniques has greater advantage in integrated arrangement nuclear reactor.
3, the built-in CRDM that the present embodiment provides, operation principle is identical with the CRDM of external, but whole CRDM is placed in inside pressure vessel and works close to core region, to there is provided runner reasonable distribution flow for reactor coolant, therefore structural design to differ greatly with CRDM conventional at present:
1) due to inside and outside built-in CRDM equipment without pressure reduction, its external shell parts are no longer belong to primary Ioops pressure boundary, and original pressure-bearing shell designing requirement can be greatly reduced.
2) original external split yoke is owing to adopting box-structure, and sectional area is excessive, and this structure is placed on the resistance that can be greatly increased runner inside pressure vessel, it is necessary to adopt the magnetic yoke structure with more small bore.
3) adopt built-in CRDM, after its actuating coil is placed in coolant, the waterproof sealing of electric component need to be considered, adopt integrated sealing form to have simple in construction, the advantage that reliability is high.
4) in order to reduce CRDM and the contact area installing locating flange, it is effectively increased the runner perforated area installed on locating flange, driving mechanism is installed to adopt between locating flange with CRDM and is threadeded, it also avoid the welding residual stress adopting welding to cause and base deformation simultaneously, simple in construction, it is simple to change, keep in repair and storage.
In this specification, each embodiment adopts the mode gone forward one by one to describe, and what each embodiment stressed is the difference with other embodiments, between each embodiment identical similar portion mutually referring to.For system disclosed in embodiment, owing to corresponding to the method disclosed in Example, so what describe is fairly simple, relevant part illustrates referring to method part.
Those skilled in the art specifically can should be used for using different methods to realize described function to each, but this realization is it is not considered that beyond the scope of this invention.
Obviously, invention can be carried out various change and modification without deviating from the spirit and scope of the present invention by those skilled in the art.So, if these amendments of the present invention and modification belong within the scope of the claims in the present invention and equivalent technologies thereof, then the present invention is also intended to include these change and modification.
Claims (5)
1. a built-in CRDM, it is characterised in that including:
Pressure-bearing case member；Described pressure-bearing case member, by being axially divided into three sections from top to bottom, is made up of rod stroke housing, hook housing and guide thimble；Adopt threaded between described rod stroke housing and described hook housing, adopt between described hook housing and described guide thimble and threaded；
Magnetic inversion line coil component；Described magnetic inversion line coil component is sleeved on outside described pressure-bearing case member；
Hook parts；Described hook parts are arranged in described pressure-bearing case member；And
Drive-rod part；Described drive-rod part is arranged on inside described pressure-bearing case member.
2. built-in CRDM as claimed in claim 1, it is characterised in that described hook parts by promoting magnetic pole, pawl magnetic pole, pawl armature, determine pawl magnetic pole, determine pawl armature, hook and quill and form；Described lifting magnetic pole, pawl magnetic pole, pawl armature, determine pawl magnetic pole, determine pawl armature, hook is sleeved on described quill.
3. built-in CRDM as claimed in claim 1, it is characterised in that described magnetic inversion line coil component is made up of a yoke assembly and three actuating coils.
4. built-in CRDM as claimed in claim 3, it is characterised in that described yoke assembly is monoblock type cylindrical structure form.
5. built-in CRDM as claimed in claim 1, it is characterised in that described hook housing adopts with locating flange threadeds.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610298040.8A CN105788669A (en) | 2016-05-06 | 2016-05-06 | Built-in type control bar driving mechanism |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610298040.8A CN105788669A (en) | 2016-05-06 | 2016-05-06 | Built-in type control bar driving mechanism |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN105788669A true CN105788669A (en) | 2016-07-20 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610298040.8A Pending CN105788669A (en) | 2016-05-06 | 2016-05-06 | Built-in type control bar driving mechanism |
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| 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 |
| CN106898388A (en) * | 2017-03-09 | 2017-06-27 | 华北电力大学 | A kind of device for preventing reactor from control rod ejection accident occurring |
| CN107665741A (en) * | 2017-11-01 | 2018-02-06 | 上海核工程研究设计院有限公司 | A kind of control rod for nuclear reactor component is kept and release structure |
| CN108922637A (en) * | 2018-07-25 | 2018-11-30 | 中广核研究院有限公司 | A kind of nuclear power station-service control rod drive mechanism |
| CN110815132A (en) * | 2019-12-10 | 2020-02-21 | 上海第一机床厂有限公司 | Novel reactor control rod driving mechanism claw assembly and assembling method |
| CN112002444A (en) * | 2020-07-31 | 2020-11-27 | 清华大学 | Hydraulic cylinder positioning structure and built-in control rod driving mechanism |
| CN112017799A (en) * | 2020-07-31 | 2020-12-01 | 清华大学 | Rod position measuring pressure bearing shell with adapter and control rod hydraulic drive system |
| CN112071447A (en) * | 2020-08-27 | 2020-12-11 | 清华大学 | Built-in control rod driving wire |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH06235785A (en) * | 1993-02-09 | 1994-08-23 | Toshiba Corp | Control rod drive mechanism |
| US20120148007A1 (en) * | 2010-12-09 | 2012-06-14 | Westinghouse Electric Company Llc | Nuclear reactor internal electric control rod drive mechanism assembly |
| CN104269192A (en) * | 2014-10-16 | 2015-01-07 | 中国科学院合肥物质科学研究院 | Rod drop control actuator suitable for liquid metal cooling reactor |
| CN205751538U (en) * | 2016-05-06 | 2016-11-30 | 上海核工程研究设计院 | A kind of built-in CRDM |
-
2016
- 2016-05-06 CN CN201610298040.8A patent/CN105788669A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH06235785A (en) * | 1993-02-09 | 1994-08-23 | Toshiba Corp | Control rod drive mechanism |
| US20120148007A1 (en) * | 2010-12-09 | 2012-06-14 | Westinghouse Electric Company Llc | Nuclear reactor internal electric control rod drive mechanism assembly |
| CN104269192A (en) * | 2014-10-16 | 2015-01-07 | 中国科学院合肥物质科学研究院 | Rod drop control actuator suitable for liquid metal cooling reactor |
| CN205751538U (en) * | 2016-05-06 | 2016-11-30 | 上海核工程研究设计院 | A kind of built-in CRDM |
Cited By (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN106205748B (en) * | 2016-08-31 | 2018-05-18 | 中国核动力研究设计院 | Reactor control rod driving mechanism |
| 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 |
| CN106898388A (en) * | 2017-03-09 | 2017-06-27 | 华北电力大学 | A kind of device for preventing reactor from control rod ejection accident occurring |
| CN106898388B (en) * | 2017-03-09 | 2018-07-24 | 华北电力大学 | A kind of device for preventing reactor from control rod ejection accident occurs |
| CN107665741A (en) * | 2017-11-01 | 2018-02-06 | 上海核工程研究设计院有限公司 | A kind of control rod for nuclear reactor component is kept and release structure |
| CN108922637A (en) * | 2018-07-25 | 2018-11-30 | 中广核研究院有限公司 | A kind of nuclear power station-service control rod drive mechanism |
| CN110815132A (en) * | 2019-12-10 | 2020-02-21 | 上海第一机床厂有限公司 | Novel reactor control rod driving mechanism claw assembly and assembling method |
| CN112002444A (en) * | 2020-07-31 | 2020-11-27 | 清华大学 | Hydraulic cylinder positioning structure and built-in control rod driving mechanism |
| CN112017799A (en) * | 2020-07-31 | 2020-12-01 | 清华大学 | Rod position measuring pressure bearing shell with adapter and control rod hydraulic drive system |
| CN112017799B (en) * | 2020-07-31 | 2022-03-11 | 清华大学 | Rod position measuring pressure bearing shell with adapter and control rod hydraulic drive system |
| CN112002444B (en) * | 2020-07-31 | 2022-09-09 | 清华大学 | Hydraulic cylinder positioning structure and built-in control rod driving mechanism |
| CN112071447A (en) * | 2020-08-27 | 2020-12-11 | 清华大学 | Built-in control rod driving wire |
| CN112071447B (en) * | 2020-08-27 | 2022-09-09 | 清华大学 | Built-in control rod driving wire |
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| CB02 | Change of applicant information | ||
| CB02 | Change of applicant information |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |
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| TA01 | Transfer of patent application right | ||
| TA01 | Transfer of patent application right |
Effective date of registration: 20181018 Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Applicant after: Shanghai Shen Nuclear Energy Engineering Technology Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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| CB02 | Change of applicant information | ||
| CB02 | Change of applicant information |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Applicant after: Shanghai Shen Nuclear Energy Engineering Technology Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Applicant before: Shanghai Shen Nuclear Energy Engineering Technology Co.,Ltd. |
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| WD01 | Invention patent application deemed withdrawn after publication | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20160720 |