CN103065692B - Safety rod driving system of liquid heavy metal cooling reactor - Google Patents
Safety rod driving system of liquid heavy metal cooling reactor Download PDFInfo
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- CN103065692B CN103065692B CN201310019578.7A CN201310019578A CN103065692B CN 103065692 B CN103065692 B CN 103065692B CN 201310019578 A CN201310019578 A CN 201310019578A CN 103065692 B CN103065692 B CN 103065692B
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- Prior art keywords
- release lever
- carriage release
- heavy metal
- safe cluster
- reactor core
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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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Abstract
The invention discloses a safety rod driving system of a liquid heavy metal cooling reactor, which belongs to the field of nuclear reactor equipment. The system comprises a motor (1), a rod position indicator (2), a transmission rod (30), a movable damper (4), a gripping device (5), an electromagnet (7), a moving rod guide tube (10), a moving rod (12), a control rod baffle plate (13), another gripping device (15) and a shell (6). According to the safety rod driving system, the safety rod is positioned at the lower end of a reactor core in power operation on the basis of the characteristics that a liquid heavy metal solution is large in density and an object bears large buoyancy in the liquid heavy metal solution; and under an emergency working condition, the safety rod is inserted into the reactor core by virtue of the buoyancy, and the safe reactor shutdown is realized. The safety rod driving system meets the requirements on shutdown of the nuclear reactor, and is simple in structure, reliable and convenient to repair.
Description
Technical field
The present invention relates to reactor equipment field, belong to reactor engineering technical field, be specifically related to a kind of safety rod drive system of liquid heavy metal cooled reactor.
Background technology
The cooling medium that liquid heavy metal cooled reactor adopts is liquid heavy metal, as conventional lead bismuth alloy eutectic mixture (lead accounts for ~ 44%, bismuth accounts for ~ and 56%, fusing point ~ 125 DEG C, boiling point is 1670 DEG C), because plumbous bismuth eutectic mixture has higher, import and export coolant temperature far below boiling point, this allows the pressure of primary Ioops lower, the design of reactor assembly is simplified, adds the reliability of reactor assembly simultaneously.The chemical activity of plumbous bismuth cooling medium is low, in steam generator, relates to primary Ioops sealing and loses and the contingency procedure of loop internal leakage, there will not be hydrogen to gather, fire and blast.
The density of liquid heavy metal is large, and the density as plumbous bismuth eutectic mixture is 10.27g/cm
3, and the solid density of the principal ingredient boron carbide of safety rod is 2.519g/cm
3, the clad material outside safety rod generally adopts steel, and its density is 7.8 ~ 7.9g/cm
3, so the density of the density ratio liquid heavy metal of safety rod is little many, during safety rod drive system emergency work condition in common water-water reactor and sodium-cooled fast reactor, general free gravity falls to reactor core.So the safety rod drive system in common water-water reactor and sodium-cooled fast reactor can not directly apply to liquid heavy metal cooled reactor.
Summary of the invention
How the technical problem to be solved in the present invention: consider that liquid heavy metal solution density is large, insert reactor core when generation emergency condition quickly and accurately by safety rod, realize safe shutdown.
In order to solve the problems of the technologies described above, the technical solution used in the present invention is: a kind of safety rod drive system of liquid heavy metal cooled reactor, comprise motor, rod position indicator, drive link, electromagnet, two cover grabbing devices, control rod barrier plate, active damping device, carriage release lever, carriage release lever conduit and shell, it is characterized in that: the motor of described drive system drives drive link, drive link lower end is provided with grabbing device, it is carriage release lever below grabbing device, carriage release lever is through ring electromagnet, the lower end of carriage release lever is provided with grabbing device, it is safe cluster below grabbing device, active damping device is positioned at above electromagnet, control rod barrier plate is positioned at the upper end of the outer guide pipe of safety rod assembly, under normal power ruuning situation, carriage release lever corrects and contacts with electromagnet, safe cluster is just in time positioned at below reactor core active region, the spacing of carriage release lever upper end and active damping device just in time equals the height of reactor core active region, the spacing of safe cluster upper end and control rod barrier plate just in time equals the height of reactor core active region.
The function of each building block is as follows:
Motor:
Motor is the power source of whole safety rod drive system, and motor drives drive link, is pressed down by carriage release lever, thus safe cluster is moved the below of reactor core.
Rod position indicator:
Measure and display bar position.
Drive link:
The effect of drive link is exactly by the power transmission of motor to carriage release lever, safe cluster is moved to the below of reactor core.
Electromagnet:
When normal reactor operation, electromagnet is energized, and produces electromagnetic force, acts on the upper end of carriage release lever, overcomes safe cluster and carriage release lever and overcomes its buoyancy in liquid heavy metal solution, make safe cluster remain on the below of reactor core.Under emergency work condition, electromagnet power-off, carriage release lever and safe cluster stressed unbalance, safe cluster and carriage release lever will move upward, thus safe cluster quick insertion reactor core.
Control rod barrier plate:
During emergency shut-down, safe cluster and carriage release lever rely on buoyancy to move upward, and when safe cluster moves to reactor core, safe cluster is blocked in reactor core position by control rod barrier plate together with active damping device.
Active damping device:
When normal reactor operation and emergency shut-down two kinds of operating modes, active damping device is in the state of propping, when emergency shut-down, safe cluster and carriage release lever rely on buoyancy to move upward, when safe cluster moves to reactor core, safe cluster is blocked in reactor core position by control rod barrier plate together with active damping device.Active damping device plays buffer action.Active damping device must be packed up when reloading, so that carriage release lever moves on continuing, shifting out reactor core.
Carriage release lever:
Carriage release lever hollow structure, lower end is connected with safe cluster by grabbing device.
Carriage release lever conduit:
Above be connected with large rotating plug, Xia Yu center measurement column connects, and effect is carriage release lever guiding.
Grabbing device:
There are two cover grabbing devices, are a set ofly fixed on drive link, capture carriage release lever below; A set ofly be fixed on carriage release lever, capture safe cluster below.
Shell:
On large rotating plug, the parts of driving mechanism are isolated from the outside, prevent the radiomaterial piling in-core from letting out.
The characteristic that the buoyancy that the present invention utilizes object suffered in liquid heavy metal solution is large, the liquid heavy metal cooled reactor safety rod drive system designed, solves the problem how when emergency work condition, safety rod being inserted quickly and accurately reactor core.The present invention meets the shutdown demand of nuclear reactor completely, and principle of work is simple, and structure is simple, and system reliability is high.
Accompanying drawing explanation
Fig. 1 is safety rod driving system structure figure of the present invention;
Fig. 2 is that safety rod drive system of the present invention plays heap procedure chart;
Fig. 3 is that safety rod drive system of the present invention is reloaded procedure chart;
Fig. 4 is safety rod drive system emergency shut-down procedure chart of the present invention;
In figure: 1. motor, 2. rod position indicator, 3. drive link, 4. active damping device, 5. grabbing device, 6. shell, 7. electromagnet, 8. large rotating plug, 9 liquid heavy metal liquid level of solution, 10. carriage release lever conduit, 11. measurement column bottom surfaces, center, 12. carriage release levers, 13. control rod barrier plates, 14. reactor core active regions, 15. grabbing devices, 16. safe clusters.
Embodiment
Concrete structure of the present invention and embodiment is described in detail below in conjunction with accompanying drawing.
The safety rod drive system specific works mode of a kind of liquid heavy metal of the present invention cooled reactor is as follows:
Play heap:
Carriage release lever 12 locks together by the grabbing device 5 on drive link, motor 1 drives drive link 3, press down carriage release lever 12, the safe cluster 16 be connected with carriage release lever 12 is moved down gradually, when effective district of safe cluster 16 is completely below reactor core, carriage release lever 12 corrects and arrives electromagnet 7 place, electromagnet 7 is energized, the magnetic force produced produces binding force to carriage release lever 12, and carriage release lever 12 relies on the constraint of electromagnet 7 to overcome buoyancy.Grabbing device 5 on drive link 3 unclamps, and motor 1 drives drive link 3 to rise to active damping device 4 position.
Power operation:
During Power operation, as shown in Figure 3, carriage release lever 12 relies on the constraint of electromagnet 7 to overcome buoyancy to the state of safety rod drive system, and safe cluster 16 is below reactor core, and drive link 3 and carriage release lever 12 depart from, and rise to active damping device 4 position.
Emergency work condition:
Electromagnet 7 power-off, carriage release lever 12 loses the binding force of electromagnet 7 to it, carriage release lever 12 and safe cluster 16 in the vertical direction are by force unbalance, buoyancy is greater than self gravity, carriage release lever 12 and safe cluster 16 rely on buoyancy to move upward, when safe cluster 16 inserts reactor core active region 14 completely, safe cluster 16 keeps off in reactor core active region 14 by active damping plate 4 and control rod barrier plate 13 jointly, realizes safe shutdown.
Reload, keep in repair operating mode:
From Power operation operating mode to operating mode of reloading, motor 1 drives drive link 3 to move downward, and moves to carriage release lever 12 position, and carriage release lever 12 is locked by the grabbing device 5 on drive link 3, and disconnect electromagnet 7, motor 1 drives drive link 3 slowly to rise.When safe cluster 16 inserts reactor core completely, the grabbing device 15 of carriage release lever 12 lower end unclamps, and carriage release lever 12 and safe cluster 16 depart from, and active damping plate 4 is packed up simultaneously, motor 1 continues to drive drive link 3 slowly to rise, until carriage release lever 12 is enough to reload with the space of reactor core.
Reload after terminating, motor 1 drives drive link 3 slowly to decline, until carriage release lever 12 contacts with safe cluster 16, safe cluster 16 is locked by the grabbing device 15 on carriage release lever 12, and active damping plate 4 ejects, and has then carried out piling action.
The part that the present invention does not elaborate belongs to techniques well known.
Although be described the illustrative embodiment of the present invention above; so that the technician of this technology neck understands the present invention; but should be clear; the invention is not restricted to the scope of embodiment; to those skilled in the art; as long as various change to limit and in the spirit and scope of the present invention determined, these changes are apparent, and all innovation and creation utilizing the present invention to conceive are all at the row of protection in appended claim.
Claims (8)
1. the safety rod drive system of a liquid heavy metal cooled reactor, it is characterized in that: comprise motor (1), rod position indicator (2), drive link (3), active damping device (4), first grabbing device (5), shell (6), electromagnet (7), carriage release lever conduit (10), carriage release lever (12), control rod barrier plate (13) and the second grabbing device (15), the motor (1) of described drive system drives drive link (2), drive link (2) lower end is provided with the first grabbing device (5), first grabbing device (5) is carriage release lever (12) below, carriage release lever (12) is through electromagnet (7), electromagnet (7) is ring electromagnet, the lower end of carriage release lever (12) is provided with the second grabbing device (15), second grabbing device (15) is safe cluster (16) below, active damping device (4) is positioned at electromagnet (7) top, control rod barrier plate (13) is positioned at the upper end of safe cluster (16) outer guide pipe, under normal power ruuning situation, carriage release lever (12) corrects and contacts with electromagnet (7), safe cluster (16) is just in time positioned at below, reactor core active region (14), the spacing of carriage release lever (12) upper end and active damping device (4) just in time equals the height of reactor core active region (14), the spacing of safe cluster (16) upper end and control rod barrier plate (13) just in time equals the height of reactor core active region (14).
2. the safety rod drive system of a kind of liquid heavy metal cooled reactor according to claim 1, it is characterized in that: described motor is the power source of whole safety rod drive system, motor drives drive link, is pressed down by carriage release lever, thus safe cluster is moved to the below of reactor core.
3. the safety rod drive system of a kind of liquid heavy metal cooled reactor according to claim 1, is characterized in that: described excellent position indicator is used for measuring and display bar position.
4. the safety rod drive system of a kind of liquid heavy metal cooled reactor according to claim 1, is characterized in that: the effect of described drive link is exactly by the power transmission of motor to carriage release lever, safe cluster is moved to the below of reactor core.
5. the safety rod drive system of a kind of liquid heavy metal cooled reactor according to claim 1, it is characterized in that: described electromagnet, when normal reactor operation, electromagnet is energized, produce electromagnetic force, act on the upper end of carriage release lever, overcome safe cluster and carriage release lever and overcome its buoyancy in liquid heavy metal solution, make safe cluster remain on the below of reactor core active region; Under emergency work condition, electromagnet power-off, carriage release lever and safe cluster stressed unbalance, safe cluster and carriage release lever will move upward, thus safe cluster quick insertion reactor core.
6. the safety rod drive system of a kind of liquid heavy metal cooled reactor according to claim 1, it is characterized in that: described control rod barrier plate, during emergency shut-down, safe cluster and carriage release lever rely on buoyancy to move upward, when safe cluster moves to reactor core, safe cluster is blocked in reactor core position by control rod barrier plate together with active damping device.
7. the safety rod drive system of a kind of liquid heavy metal cooled reactor according to claim 1, it is characterized in that: described active damping device, when normal reactor operation and emergency shut-down two kinds of operating modes, active damping device is in the state of propping, when emergency shut-down, safe cluster and carriage release lever rely on buoyancy to move upward, when safe cluster moves to reactor core, safe cluster is blocked in reactor core position by control rod barrier plate together with active damping device, active damping device plays buffer action, active damping device must be packed up when reloading, so that carriage release lever moves on continuing, shift out reactor core.
8. the safety rod drive system of a kind of liquid heavy metal cooled reactor according to claim 1, is characterized in that: described carriage release lever is hollow structure, and lower end is connected with safe cluster by the second grabbing device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310019578.7A CN103065692B (en) | 2013-01-18 | 2013-01-18 | Safety rod driving system of liquid heavy metal cooling reactor |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310019578.7A CN103065692B (en) | 2013-01-18 | 2013-01-18 | Safety rod driving system of liquid heavy metal cooling reactor |
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| CN103065692A CN103065692A (en) | 2013-04-24 |
| CN103065692B true CN103065692B (en) | 2015-04-22 |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104167226B (en) * | 2014-09-05 | 2017-01-25 | 中国科学院合肥物质科学研究院 | Liquid metal cooling reactor experimental system capable of realizing critical and subcritical running test |
| CA2963621C (en) * | 2014-10-12 | 2018-04-24 | Ian Richard Scott | Reactivity control in a molten salt reactor |
| CN104269192B (en) * | 2014-10-16 | 2017-06-06 | 中国科学院合肥物质科学研究院 | A kind of control scram executing agency suitable for liquid-metal cooled reactor |
| CN106409350B (en) * | 2016-11-02 | 2018-09-28 | 中广核研究院有限公司 | System is protected in the emergency shut-down of one heavy metal species cooled reactor |
| CN107507653A (en) * | 2017-08-29 | 2017-12-22 | 华北电力大学 | A kind of Lead cooled fast breeder reactor separates reactor core embodiment |
| CN112037943B (en) * | 2020-07-28 | 2023-03-14 | 中国原子能科学研究院 | Hydraulic suspension split type passive shutdown assembly for fast neutron reactor |
| CN114188051B (en) * | 2021-12-03 | 2024-02-20 | 中国原子能科学研究院 | Method and device for monitoring position of safety bar |
| CN114188047B (en) * | 2021-12-03 | 2024-05-14 | 中国原子能科学研究院 | Reactivity control device |
| CN114171214B (en) * | 2021-12-03 | 2024-02-20 | 中国原子能科学研究院 | Control rod system for critical device |
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Patent Citations (7)
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| US3905634A (en) * | 1974-06-04 | 1975-09-16 | Us Energy | Quick release latch for reactor scram |
| US4314881A (en) * | 1980-03-18 | 1982-02-09 | The United States Of America As Represented By The United States Department Of Energy | Reactor control rod timing system |
| JPS6176985A (en) * | 1984-09-21 | 1986-04-19 | 株式会社東芝 | Driving mechanism of control rod |
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| CN103065692A (en) | 2013-04-24 |
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Granted publication date: 20150422 Termination date: 20210118 |