CN111933314A - Passive shutdown device for nuclear reactor - Google Patents
Passive shutdown device for nuclear reactor Download PDFInfo
- Publication number
- CN111933314A CN111933314A CN202010788746.9A CN202010788746A CN111933314A CN 111933314 A CN111933314 A CN 111933314A CN 202010788746 A CN202010788746 A CN 202010788746A CN 111933314 A CN111933314 A CN 111933314A
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- control rod
- reactor
- rod
- bearing shell
- core
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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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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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a passive shutdown device of a nuclear reactor, which comprises a pressure bearing shell (1), a reactor control rod (2), a control rod drive rod (3), a linear bearing (4), a metal corrugated pipe (5) and a control rod drive mechanism (6); the pressure bearing shell (1) is internally of a hollow structure and provides a space for the movement of the reactor control rod (2); the control rod drive rod (3) is used for driving the reactor control rod (2) to move in the pressure bearing shell (1); the linear bearing (4) is used for radially limiting the control rod drive rod (3) and allowing the control rod drive rod to axially slide at the same time, so that the control rod can move in a reactor core. The device is not influenced by the flowing of in-core coolant or buoyancy, the control rod can be quickly inserted into the reactor core, and the response speed is high; independent of gravity, while being suitable for vertical or horizontal arrangements of the reactor core.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor engineering, and particularly relates to the technical field of reactor core control and shutdown of a reactor.
Background
In order to ensure safe and reliable operation of a nuclear reactor, a corresponding system must be provided to perform reactive control and protection functions. The important function of the reactor reactivity control system is to ensure the safety of the reactor, and the control protection system can rapidly act to ensure the safe shutdown of the reactor in case of accidents or emergencies. In the current reactor design, the most common reactivity control method is to adopt a control rod, namely, an absorption rod made of a material with a large neutron absorption cross section is inserted into a reactor core through a transmission mechanism to absorb neutrons in the reactor core, so that the reactor core reactivity is reduced, and the safety shutdown function is realized.
In order to allow the control rods to be reliably inserted into the core in the event of an accident, the control rod drive device is required to be able to insert the control rods into the core even in the event of a power loss, thereby ensuring the safety of the core. The traditional reactor mainly depends on the action of gravity, and when a control rod driving mechanism loses power, the control rods fall into a reactor core by utilizing the gravity of the control rod driving mechanism, so that the purpose of passive shutdown (independent of external driving force of a system) is achieved.
For a conventional vertically arranged reactor, the dropping of control rods into the core may be affected by the flow of coolant inside the core, buoyancy, etc., causing uncertainty in the insertion speed. For some special-purpose reactors, the reactor core may not be in a vertical state under the normal operation condition, so that a control rod relying on the action of gravity cannot be smoothly inserted into the reactor core under the accident condition, the passive shutdown cannot be realized, and the reactivity safety cannot be met. Other passive principles are required for realizing the control rod insertion and the safety shutdown function.
Disclosure of Invention
The invention provides a reactor passive shutdown device, which can automatically insert reactor control rods into a reactor core by utilizing the internal and external pressure difference, an elastic sealing element, a sliding mechanism and the like of the device when a control rod driving mechanism loses power, thereby reducing the reactor core reactivity and realizing the reactor shutdown. The device comprises a pressure bearing shell (1), a reactor control rod (2), a control rod drive rod (3), a linear bearing (4), a metal corrugated pipe (5) and a control rod drive mechanism (6); the pressure bearing shell (1) is internally of a hollow structure and provides a space for the movement of the reactor control rod (2); the reactor control rod (2) is made of neutron absorber materials, so that the reactor core reactivity can be reduced; one end of the control rod drive rod (3) is connected with the reactor control rod (2), and the other end of the control rod drive rod (3) is connected with the drive mechanism (6) and can be used for driving the reactor control rod (2) to move in the pressure bearing shell (1); the linear bearing (4) consists of a steel ball and a retainer, and the linear bearing (4) radially limits the control rod drive rod (3) and allows the control rod drive rod to axially slide so as to realize the movement of the control rod in the reactor core; the metal corrugated pipe (5) is formed by connecting a plurality of metal diaphragms into a tubular shape, one end of the metal corrugated pipe (5) is connected to the control rod drive rod (3), and the other end of the metal corrugated pipe (5) is connected to the pressure bearing shell (1); the control rod driving mechanism (6) drives the reactor control rod (2) to be inserted into or pulled out of the reactor core through the control rod driving rod (3).
Preferably, the internal space of the pressure-bearing shell (1) is a sealed vacuum environment.
Preferably, the metal bellows (5) seals the pressure-bearing shell (1).
Preferably, the control rod drive mechanism (6) includes a drive motor and a finger member by which the control rod drive mechanism (6) grips or releases the control rod drive rod (3).
Under the condition of an accident (power failure of a driving mechanism), on one hand, the device automatically presses the reactor control rod (2) into the reactor core by utilizing the pressure difference between the inside and the outside of the pressure-bearing shell; on the other hand, the metal corrugated pipe (5) has elasticity and can provide extra thrust to push the reactor control rods (2) into the reactor core, so that passive shutdown of the reactor is realized.
Under the accident condition, the device does not need electric power or manual drive, and reactor control rods can be automatically inserted into a reactor core to realize passive shutdown; the device is not influenced by the flowing of in-core coolant or buoyancy, the control rod can be quickly inserted into the reactor core, and the response speed is high; the device does not depend on the action of gravity, and is suitable for vertically or horizontally arranging the reactor core; the interior of the device is in a vacuum state, and the automatic insertion of the control rod is realized by directly utilizing the pressure difference between the environment and the interior; the device utilizes the metal corrugated pipe to seal the moving part and the static part, and simultaneously utilizes the elasticity of the metal corrugated pipe to provide extra control rod insertion driving force; the device utilizes the linear bearing to realize the radial limit and the axial sliding of the control rod, and reduces the moving friction resistance of the control rod.
Drawings
FIG. 1 is a structure of a reactor passive shutdown device.
Fig. 2 is a bellows installation connection.
FIG. 3 is a horizontal arrangement core passive shutdown device.
FIG. 4 is a vertically arranged passive reactor shutdown device for a reactor core.
Wherein: 1-pressure bearing shell 2-reactor control rod 3-control rod drive rod 4-linear bearing 5-metal bellows 6-control rod drive mechanism 7-reactor core.
Detailed Description
In order to make the aforementioned objects, features and advantages of the present invention comprehensible, embodiments accompanied with figures are described in further detail below.
As shown in fig. 1, the passive reactor shutdown device mainly comprises a pressure-bearing shell 1, a reactor control rod 2, a control rod drive rod 3, a linear bearing 4, a metal corrugated pipe 5, a control rod drive mechanism 6 and the like.
The pressure-bearing shell 1 is a hollow column structure, and the reactor control rod 2, the control rod drive rod 3, the linear bearing 4 and the metal corrugated pipe 5 are arranged in a cylindrical space in the pressure-bearing shell. The control rod driving mechanism 6 is arranged outside the pressure bearing shell, and one end of the control rod driving rod 3 extends out of the pressure bearing shell and is connected with a claw structure of the driving mechanism.
The reactor control rod 2 is coaxially connected with a control rod driving rod 3, a linear bearing 4 is arranged on the control rod driving rod 3 close to one end of the control rod, the driving rod penetrates through the linear bearing and is fixed, and the linear bearing can slide in the pressure-bearing shell.
As shown in fig. 2, a metal corrugated pipe 5 is installed inside the other end of the pressure-bearing shell in such a way that the metal corrugated pipe is arranged in the pressure-bearing shell 1, one end of the metal corrugated pipe 5 is connected and sealed with the end of the pressure-bearing shell, the control rod drive rod 3 penetrates through the corrugated pipe, the other end of the metal corrugated pipe 5 is connected and sealed with the control rod drive rod 3, a closed space (vacuum pumping) is formed inside the pressure-bearing shell 1 and outside the metal corrugated pipe 5, and the inside of the metal corrugated pipe 5 is communicated with the external environment (atmosphere) through the control rod drive rod 3 penetrating through.
The device may be horizontally arranged and inserted into the reactor core in the manner shown in figure 3, wherein the end with the reactor control rods 2 is located in the reactor core area and the other part is located outside the reactor core 7; the reactor control rods 2 are axially and horizontally slidable within the pressure-bearing shell 1 by means of linear bearings 4 mounted on the control rod drive rods 3.
Before the device is installed and used, the pressure bearing shell 1 is vacuumized, and due to the internal and external pressure difference and the elastic action of the metal corrugated pipe 5, the control rod driving rod 3 receives the thrust to the reactor core, so that the reactor control rod 2 is kept inserted into the reactor core before the driving mechanism acts.
In normal operation, in order to provide sufficient reactivity to the reactor, the reactor control rods 2 are lifted out of the core, and the control rod drive rods 3 are pulled out of the core together with the reactor control rods 2 by the driving force of the external drive motor, thereby maintaining the state in which the reactor control rods 2 are lifted out of the core.
In an accident situation (loss of power to the drive mechanism), the reactor control rods 2 need to be inserted into the core quickly to reduce the reactivity of the core and ensure reactor shutdown. At the moment, the driving mechanism is loosened after power failure, the control rod driving rod can quickly push the control rod into the reactor core under the action of pressure difference and the elasticity of the corrugated pipe, so that the reactor is shut down, and the safety of the reactor is ensured.
The apparatus may be vertically arranged and inserted into the core of a reactor in the manner shown in figure 4, wherein the end with the control rods is located in the core region and the other part is located outside the core, and the reactor control rods 2 are axially vertically movable within the pressure containment vessel 1.
Before the device is installed and used, the pressure bearing shell 1 is vacuumized, and due to the internal and external pressure difference and the elastic action of the metal corrugated pipe 5, the control rod driving rod 3 receives the thrust to the reactor core, so that the reactor control rod 2 is kept inserted into the reactor core before the driving mechanism 6 acts.
In normal operation, in order to provide sufficient reactivity to the reactor, the reactor control rods 2 are lifted out of the core, and the driving rods together with the reactor control rods 2 are pulled out of the core by the driving force of the external driving motor, and the state in which the reactor control rods 2 are lifted out of the core is maintained.
In an accident situation (loss of power to the drive mechanism), the reactor control rods 2 need to be inserted into the core quickly to reduce the reactivity of the core and ensure reactor shutdown. At the moment, the driving mechanism 6 is released due to power loss, the control rod driving rod 3 rapidly pushes the reactor control rod 2 into the reactor core under the action of pressure difference and the elastic force of the metal corrugated pipe 5, so that the reactor is shut down, and the safety of the reactor is ensured.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations. The foregoing examples or embodiments are merely illustrative of the present invention, which may be embodied in other specific forms or in other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.
Claims (4)
1. A passive shutdown device of a nuclear reactor is characterized by comprising a pressure bearing shell (1), a reactor control rod (2), a control rod drive rod (3), a linear bearing (4), a metal corrugated pipe (5) and a control rod drive mechanism (6);
the pressure bearing shell (1) is internally of a hollow structure and provides a space for the movement of the reactor control rod (2);
the reactor control rod (2) is made of neutron absorber materials, so that the reactor core reactivity can be reduced;
one end of the control rod drive rod (3) is connected with the reactor control rod (2), and the other end of the control rod drive rod (3) is connected with the drive mechanism (6) and can be used for driving the reactor control rod (2) to move in the pressure bearing shell (1);
the linear bearing (4) consists of a steel ball and a retainer, and the linear bearing (4) radially limits the control rod drive rod (3) and allows the control rod drive rod to axially slide so as to realize the movement of the control rod in the reactor core;
the metal corrugated pipe (5) is formed by connecting a plurality of metal diaphragms into a tubular shape, one end of the metal corrugated pipe (5) is connected to the control rod drive rod (3), and the other end of the metal corrugated pipe (5) is connected to the pressure bearing shell (1);
the control rod driving mechanism (6) drives the reactor control rod (2) to be inserted into or pulled out of the reactor core through the control rod driving rod (3).
2. A nuclear reactor passive shutdown device according to claim 1, characterized in that the internal space of the pressure-bearing shell (1) is a sealed vacuum environment.
3. A nuclear reactor passive shutdown device according to claim 1, characterized in that the metal bellows (5) seals the pressure-bearing shell (1).
4. A nuclear reactor passive shutdown device as claimed in claim 1, wherein the control rod drive mechanism (6) includes a drive motor and a finger member by which the control rod drive mechanism (6) grips or releases the control rod drive rod (3).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010788746.9A CN111933314B (en) | 2020-08-07 | 2020-08-07 | Passive shutdown device for nuclear reactor |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010788746.9A CN111933314B (en) | 2020-08-07 | 2020-08-07 | Passive shutdown device for nuclear reactor |
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| CN111933314A true CN111933314A (en) | 2020-11-13 |
| CN111933314B CN111933314B (en) | 2022-05-10 |
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| CN202010788746.9A Active CN111933314B (en) | 2020-08-07 | 2020-08-07 | Passive shutdown device for nuclear reactor |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113345606A (en) * | 2021-04-28 | 2021-09-03 | 岭东核电有限公司 | Reactor shutdown control rod and reactor shutdown and cooling integrated system with same |
| CN114171214A (en) * | 2021-12-03 | 2022-03-11 | 中国原子能科学研究院 | Control rod system for critical apparatus |
| CN114420323A (en) * | 2021-11-30 | 2022-04-29 | 中国船舶重工集团公司第七一九研究所 | Non-kinetic energy safety system of reactor, reactor and ocean energy system |
| CN115841881A (en) * | 2022-11-30 | 2023-03-24 | 中国原子能科学研究院 | Reactor control rod drive mechanism |
| CN115841881B (en) * | 2022-11-30 | 2024-05-31 | 中国原子能科学研究院 | Reactor control rod driving mechanism |
Citations (5)
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| GB1344013A (en) * | 1970-06-18 | 1974-01-16 | Asea Atom Ab | Control rod drive for a water cooled nuclear reactor |
| CN1515011A (en) * | 2001-06-14 | 2004-07-21 | ����ͨAnp����˾ | Method and device for restoring fall-time of at least one control cluster for regulaing reactivity in core of light-water-cooled nuclear reactor |
| CN102483962A (en) * | 2009-06-10 | 2012-05-30 | 巴布科克和威尔科克斯核作业集团股份有限公司 | Control rod drive mechanism for nuclear reactor |
| CN105814642A (en) * | 2013-12-31 | 2016-07-27 | 纽斯高动力有限责任公司 | Managing nuclear reactor control rods |
| CN108039212A (en) * | 2017-12-13 | 2018-05-15 | 中国船舶重工集团公司第七〇九研究所 | A kind of upper-part in-reactor component suitable for floating type reactor |
-
2020
- 2020-08-07 CN CN202010788746.9A patent/CN111933314B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1344013A (en) * | 1970-06-18 | 1974-01-16 | Asea Atom Ab | Control rod drive for a water cooled nuclear reactor |
| CN1515011A (en) * | 2001-06-14 | 2004-07-21 | ����ͨAnp����˾ | Method and device for restoring fall-time of at least one control cluster for regulaing reactivity in core of light-water-cooled nuclear reactor |
| CN102483962A (en) * | 2009-06-10 | 2012-05-30 | 巴布科克和威尔科克斯核作业集团股份有限公司 | Control rod drive mechanism for nuclear reactor |
| CN105814642A (en) * | 2013-12-31 | 2016-07-27 | 纽斯高动力有限责任公司 | Managing nuclear reactor control rods |
| CN108039212A (en) * | 2017-12-13 | 2018-05-15 | 中国船舶重工集团公司第七〇九研究所 | A kind of upper-part in-reactor component suitable for floating type reactor |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113345606A (en) * | 2021-04-28 | 2021-09-03 | 岭东核电有限公司 | Reactor shutdown control rod and reactor shutdown and cooling integrated system with same |
| CN114420323A (en) * | 2021-11-30 | 2022-04-29 | 中国船舶重工集团公司第七一九研究所 | Non-kinetic energy safety system of reactor, reactor and ocean energy system |
| CN114420323B (en) * | 2021-11-30 | 2024-05-24 | 中国船舶重工集团公司第七一九研究所 | Passive safety system of reactor, reactor and ocean energy system |
| CN114171214A (en) * | 2021-12-03 | 2022-03-11 | 中国原子能科学研究院 | Control rod system for critical apparatus |
| CN114171214B (en) * | 2021-12-03 | 2024-02-20 | 中国原子能科学研究院 | Control rod system for critical device |
| CN115841881A (en) * | 2022-11-30 | 2023-03-24 | 中国原子能科学研究院 | Reactor control rod drive mechanism |
| CN115841881B (en) * | 2022-11-30 | 2024-05-31 | 中国原子能科学研究院 | Reactor control rod driving mechanism |
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| Publication number | Publication date |
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| CN111933314B (en) | 2022-05-10 |
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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 Co.,Ltd. |