CN115148381A - Control rod driving mechanism and nuclear reactor - Google Patents
Control rod driving mechanism and nuclear reactor Download PDFInfo
- Publication number
- CN115148381A CN115148381A CN202210907383.5A CN202210907383A CN115148381A CN 115148381 A CN115148381 A CN 115148381A CN 202210907383 A CN202210907383 A CN 202210907383A CN 115148381 A CN115148381 A CN 115148381A
- Authority
- CN
- China
- Prior art keywords
- main driving
- control rod
- driving shaft
- reactor
- main
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Images
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
- G21C1/00—Reactor types
Abstract
The invention discloses a control rod driving mechanism and a nuclear reactor comprising the same, wherein the control rod driving mechanism is used for the nuclear reactor and comprises a main driving shaft, a power assembly and a constant force spring, one end of the main driving shaft is connected with a control rod, and the power assembly is used for driving the main driving shaft to move so as to drive the control rod to be inserted into or pulled out of a reactor core; the constant force spring is arranged at one end, far away from the control rod, of the main driving shaft and is fixedly connected with the main driving shaft, and when the main driving shaft drives the control rod to move towards the direction far away from the reactor core, the constant force spring is in a stretching state. The control rod driving mechanism can realize the safe rod return of the control rod without depending on gravity under the condition of power loss.
Description
Technical Field
The invention belongs to the technical field of nuclear industry, and particularly relates to a control rod driving mechanism and a nuclear reactor comprising the same.
Background
The control rod driving mechanism of nuclear reactor is one important apparatus for controlling the reactivity of the reactor core and protecting the reactor core, and can regulate the spatial position, speed and acceleration of the control rod in the reactor core to realize the operation and safety functions of starting, power regulation, normal shutdown, emergency shutdown, etc.
Control rod driving mechanisms commonly adopted by current nuclear reactors are of the types of magnetic stepping lifting type, gear rack type, ball screw type, steel wire roller type, chain roller type and the like. However, the above kind of control rod drive mechanism is installed at the upper or lower portion of the vertical reactor core, and can only achieve the movement of the control rods in the up-down direction in the spatial position. When the reactor core needs to be horizontally arranged (or not vertically arranged) under certain special requirements (such as height direction space limitation, application scenes of vehicles, ships or aircrafts and the like), or under the condition of no gravity or micro-gravity, the control rod driving mechanism is not suitable for being installed at the horizontal reactor core transverse position, or the control rod transverse space position (or the non-vertical direction position) cannot be adjusted, or under the condition that the power is lost, an external energy source cannot be used, the control rod cannot be inserted to the position where the reactor core reactivity is reduced to the safety state (the original control rod driving mechanism usually makes the control rod fall back to the safety position under the action of gravity). Therefore, aiming at a horizontal reactor or a scene that the control rod is required to be adjusted in the horizontal direction (and in the non-vertical direction), the power source composition, the structural form and the working principle of the existing control rod driving mechanism are not suitable.
Disclosure of Invention
The present invention is directed to provide a control rod drive mechanism and a nuclear reactor including the same, which can achieve safe rod return of a control rod without relying on gravity when the control rod drive mechanism is powered off.
In order to solve the problems, the invention adopts the following technical scheme:
a control rod driving mechanism is used for a nuclear reactor and comprises a main driving shaft, a power assembly and a constant force spring, wherein one end of the main driving shaft is connected with a control rod, and the power assembly is used for driving the main driving shaft to move so as to drive the control rod to be inserted into or pulled out of a reactor core; the constant force spring is arranged at one end, far away from the control rod, of the main driving shaft and is fixedly connected with the main driving shaft, and when the main driving shaft drives the control rod to move towards the direction far away from the reactor core, the constant force spring is in a stretching state.
Preferably, the power component includes drive unit and drive unit, drive unit includes driving motor, the drive unit includes speed reduction part, bevel gear pair and main drive gear, the input and the output of driving motor of speed reduction part are connected, bevel gear pair sets up on the output of speed reduction part, and bevel gear pair and main drive gear meshing, the main drive shaft be equipped with the tooth's socket on the surface, main drive gear passes through tooth's socket and main drive shaft meshing.
Preferably, the main driving gear is a friction wheel, and the main driving gear is connected with the main driving shaft in a pressing mode so as to drive the main driving shaft to move.
Preferably, the main drive shaft is disposed in a non-vertical direction, and the transmission unit is disposed in a non-vertical direction.
Preferably, the main drive shaft is disposed in a horizontal direction, and the reduction member, the bevel gear pair, and the main drive gear are disposed in the horizontal direction.
Preferably, the control device further comprises a limiting assembly, wherein the limiting assembly comprises linear bearings, the linear bearings are provided with multiple groups of straight lines, and the multiple groups of straight lines are arranged along the horizontal direction to form a linear track, so that the main driving shaft and the control rod move on the linear track.
Preferably, the control rod driving mechanism further comprises a housing assembly, the housing assembly comprises a pressure shell and a guide pipe, the main driving shaft, the power assembly and the constant force spring are all arranged in the pressure shell, two ends of the guide pipe are respectively communicated with the pressure shell and the reactor core, the control rod is arranged in the guide pipe, and one end of the main driving shaft extends out of the pressure shell and enters the guide pipe.
The invention also provides a nuclear reactor, which comprises a reactor core, a control rod and the control rod driving mechanism.
Preferably, the core is a non-vertical core.
Preferably, the control rod drive mechanism comprises a housing assembly including a pressure shell and a guide tube, the pressure shell, the guide tube and a reactor vessel in which the core is located together forming a pressure boundary of the reactor coolant so that the reactor coolant is in a sealed and controllable state.
The control rod driving mechanism can realize the function of safe rod returning under the condition of losing an external power source, expands the application range of a nuclear reactor and improves the safety of the nuclear reactor. The driving mechanism can also realize the adjustment of the position of the reactivity control rod in the transverse space (and the position in the non-vertical direction) in the reactor core, is particularly suitable for a horizontal reactor, and can be arranged in the horizontal direction of the reactor core of the horizontal reactor.
Drawings
FIG. 1 is a schematic structural view of a control rod drive mechanism in embodiment 1 of the invention;
fig. 2 is a schematic structural view of a constant force spring in embodiment 1 of the present invention.
In the figure: the reactor comprises a main driving shaft 1, a constant force spring 2, a linear bearing 3, a driving motor 4, a speed reduction component 5, a bevel gear pair 6, a main driving gear 7, a pressure shell 8, a control rod 9, a reactor vessel 10 and a reactor core 11.
Detailed Description
The technical solutions in the present invention will be described clearly and completely with reference to the accompanying drawings, and it is obvious that the described embodiments are some, but not all embodiments of the present invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the scope of the present invention.
In the description of the present invention, it should be noted that the indication of orientation or positional relationship, such as "on" or the like, is based on the orientation or positional relationship shown in the drawings, and is only for convenience and simplicity of description, and does not indicate or imply that the device or element referred to must be provided with a specific orientation, constructed and operated in a specific orientation, and thus, should not be construed as limiting the present invention.
In the description of the present invention, the terms "first" and "second" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present invention, it is to be noted that, unless otherwise explicitly specified or limited, the terms "connected," "disposed," "mounted," "fixed," and the like are to be construed broadly, e.g., as being fixedly or removably connected, or integrally connected; either directly or indirectly through intervening media, or may be interconnected between two elements. The specific meanings of the above terms in the present invention can be understood according to specific situations by those skilled in the art.
The invention provides a control rod driving mechanism, which is used for a nuclear reactor and comprises a main driving shaft, a power assembly and a constant force spring, wherein one end of the main driving shaft is connected with a control rod, and the power assembly is used for driving the main driving shaft to move so as to drive the control rod to be inserted into or pulled out of a reactor core; the constant force spring is arranged at one end, far away from the control rod, of the main driving shaft and is fixedly connected with the main driving shaft, and when the main driving shaft drives the control rod to move towards the direction far away from the reactor core, the constant force spring is in a stretching state.
The invention also provides a nuclear reactor, which comprises a reactor core, a control rod and the control rod driving mechanism.
Example 1
As shown in fig. 1, the present embodiment discloses a control rod driving mechanism for a nuclear reactor, which includes a main driving shaft 1, a power assembly, and a constant force spring 2, wherein the main driving shaft 1 is a slender rod-shaped structure, one end of the main driving shaft is fixedly connected to a control rod 9, similarly, the control rod 9 is the same rod-shaped structure, and the control rod 9 is pulled out or inserted into a core 11 to control the start and shutdown of the reactor, so that a control rod channel adapted to the diameter of the control rod 9 is opened on the core 11. The power assembly is used for driving the main driving shaft 1 to move linearly, and further driving the control rods 9 to be inserted into or pulled out of the reactor core 11; the constant force spring 2 is arranged at one end of the main driving shaft 1 far away from the control rod 9 and is fixedly connected with the main driving shaft 1, and when the main driving shaft 1 drives the control rod 9 to move towards the direction far away from the reactor core 11, the constant force spring 2 is in a stretching state.
As shown in fig. 2, two constant force springs 2 are provided at one end of the main drive shaft 1 away from the control rod 9, the two constant force springs 2 are respectively fixedly connected with the end of the main drive shaft 1, and when the power assembly drives the main drive shaft 1 to move towards the direction away from the reactor core 11, the constant force springs 2 are in a stretching state. When no external power is input, the main driving shaft 1 pushes the control rod 9 to be inserted into the core 11 by means of the tensile elastic force provided by the constant force spring 2, thereby ensuring the safety of the nuclear reactor in the emergency of power failure.
In the present embodiment, the power assembly includes a drive unit including a drive motor 4 and a transmission unit including a speed reduction member 5, a bevel gear pair 6, and a main drive gear 7.
The input of reduction part 5 is connected with driving motor 4's output, and bevel gear pair 6 sets up on reduction part 5's output, and bevel gear pair 6 and main drive gear 7 mesh, and main drive shaft 1 is equipped with the tooth's socket on the surface, and main drive gear 7 passes through the tooth's socket and meshes with main drive shaft 1, and under driving motor 4's drive, main drive gear 7 drives main drive shaft 1 and is horizontal linear motion.
The main driving gear 7 can also be arranged as a friction wheel, at the moment, the tooth grooves are not arranged on the main driving shaft 1, the main driving gear 7 is connected with the main driving shaft 1 in a pressing mode, and the main driving shaft 1 is further driven to move through friction force.
Alternatively, the main drive shaft 1 is arranged in a non-vertical direction and the transmission unit is arranged in a non-vertical direction. In this embodiment, the main drive shaft 1, the speed reduction member 5, the bevel gear pair 6, and the main drive gear 7 are provided in the horizontal direction, and are adapted to be used in a horizontal nuclear reactor for pushing the control rods 9 provided in the horizontal direction to insert or withdraw the control rods into or from the core 11.
As shown in fig. 1, the crdm may further include a limiting assembly including linear bearings 3, the linear bearings 3 being provided with a plurality of sets, the linear bearings 3 being arranged in a horizontal direction to form a linear track, so that the main drive shaft 1 and the control rods 9 move on the formed linear track. Specifically, the linear bearings 3 are provided with four groups, wherein two groups are distributed at two ends of the main driving shaft 1 and used for ensuring the horizontal position of the main driving shaft 1, and the other two groups are arranged at two ends of the control rods 9 and used for ensuring the horizontal position of the control rods 9, so that the main driving shaft 1 and the control rods 9 are always positioned on the same straight line.
As shown in fig. 1, the control rod driving mechanism may further include a casing assembly, the casing assembly includes a pressure casing 8 and a guide tube, the main driving shaft 1, the power assembly and the constant force spring 2 are all disposed in the pressure casing 8, two ends of the guide tube are respectively communicated with the pressure casing 8 and the reactor core 11, the control rod 9 is disposed in the guide tube, one end of the main driving shaft 1 extends out of the pressure casing 8 and enters the guide tube, and the diameter of the pressure casing 8 is matched with the diameters of the main driving shaft 1 and the control rod 9, so as to further ensure the straightness of the control rod 9 and the main driving shaft 1.
The working process of the control rod drive mechanism in this embodiment is as follows:
by controlling the driving motor 4 to rotate forwards, the motor transmits power to the bevel gear pair 6 and the main driving gear 7 through the speed reducing component 5, so that the main driving gear 7 is driven to rotate forwards, the main driving gear 7 drives the main driving shaft 1 to move towards the direction far away from the reactor core 11, the control rod 9 is driven to be drawn out of the reactor core 11, at the moment, the reactor core 11 is in an active reaction state, and the constant force spring 2 is in a stretching state;
the driving motor 4 is controlled to rotate reversely, so that the main driving gear 7 is driven to rotate reversely, the main driving gear 7 drives the main driving shaft 1 to move towards the direction close to the reactor core 11, and further drives the control rod 9 to be inserted into the reactor core 11, at the moment, the reactor core 11 is in a closed state, and the constant force spring 2 is restored to a non-stretching state;
when emergency power failure, because driving motor 4 can not provide power, at this moment, main drive gear 7 can not drive main drive shaft 1 and carry out the return stroke motion, because when control rod 9 takes out reactor core 11, constant force spring 2 is in tensile state, the resilience force of constant force spring will drive main drive shaft 1 automatically and be linear motion, so that the elastic potential energy of constant force spring 2 can release, make the shape of constant force spring 2 resume by rectangular form and become the heliciform, the inertia force of whole mechanism and the frictional force between each part can be overcome to the resilience force of production, make main drive shaft 1 drive control rod 9 insert inside reactor core 11, make the reactivity of reactor core 11 reduce to the safety level, thereby realize the safety shutdown function automatically.
The constant force spring 2 in the power assembly of the control rod driving mechanism in the embodiment can automatically push the control rod 9 to be inserted into the reactor core 11 without depending on gravity in an emergency power-off state, so that safe shutdown is realized, and the control rod driving mechanism has high safety and application range.
Example 2
The embodiment discloses a nuclear reactor, which comprises a core 11 and control rods 9, and further comprises a control rod driving mechanism in the embodiment 1.
In the present embodiment, the core 11 is a non-vertical core, and specifically, the core 11 is a horizontal core 11.
As shown in fig. 1, the control rod drive mechanism includes a housing assembly including a pressure shell 8 and a guide tube, one end of the pressure shell 8 is communicated with one end of the guide tube, and the other end of the guide tube is communicated with a reactor vessel 10 in which a core 11 is located, which together form a pressure boundary of the reactor coolant so that the reactor coolant is in a sealed and controllable state.
The nuclear reactor in this embodiment is configured to maintain the reactor coolant in a sealed and controlled state by the pressure boundary of the reactor coolant formed by the pressure vessel 8, the guide pipe, and the reactor vessel 10.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and scope of the invention, and such modifications and improvements are also considered to be within the scope of the invention.
Claims (10)
1. A control rod drive mechanism for a nuclear reactor, comprising a main drive shaft (1), a power assembly and a constant force spring (2),
one end of the main driving shaft (1) is connected with a control rod (9),
the power assembly is used for driving the main driving shaft (1) to move so as to drive the control rod (9) to be inserted into or pulled out of the reactor core (11);
the constant force spring (2) is arranged at one end, far away from the control rod (9), of the main driving shaft (1) and is fixedly connected with the main driving shaft (1), and when the main driving shaft (1) drives the control rod (9) to move towards the direction far away from the reactor core (11), the constant force spring (2) is in a stretching state.
2. The CRDM of claim 1 wherein the power assembly comprises a drive unit and a transmission unit,
the drive unit comprises a drive motor (4),
the transmission unit comprises a speed reduction component (5), a bevel gear pair (6) and a main driving gear (7), the input end of the speed reduction component (5) is connected with the output end of the driving motor (4), the bevel gear pair (6) is arranged on the output end of the speed reduction component (5), the bevel gear pair (6) is meshed with the main driving gear (7),
tooth grooves are formed in the surface of the main driving shaft (1), and the main driving gear (7) is meshed with the main driving shaft (1) through the tooth grooves.
3. The crdm as set forth in claim 2, wherein the main driving gear (7) is a friction wheel, and the main driving gear (7) is connected with the main driving shaft (1) by pressing and drives the main driving shaft (1) to move.
4. The crdm as set forth in claim 2, wherein the main drive shaft (1) is disposed in a non-vertical direction and the transmission unit is disposed in a non-vertical direction.
5. The CRDM according to claim 4, characterized in that the main drive shaft (1) is disposed in a horizontal direction,
the speed reduction component (5), the bevel gear pair (6) and the main driving gear (7) are arranged along the horizontal direction.
6. The CRDM of claim 5 further comprising a limit stop assembly,
the limiting assembly comprises linear bearings (3), the linear bearings (3) are provided with multiple groups, and multiple groups of straight lines are arranged along the horizontal direction to form a linear track, so that the main driving shaft (1) and the control rod (9) move on the linear track.
7. The CRDM of claim 5 further comprising a housing assembly comprising a pressure shell (8) and a guide tube,
the main driving shaft (1), the power assembly and the constant force spring (2) are all arranged in the pressure shell (8),
two ends of the guide pipe are respectively communicated with the pressure shell (8) and the reactor core (11), the control rod (9) is arranged in the guide pipe, and one end of the main driving shaft (1) extends out of the pressure shell (8) and enters the guide pipe.
8. A nuclear reactor comprising a core (11) and control rods (9), and further comprising the control rod drive mechanism as set forth in any one of claims 1 to 7.
9. The nuclear reactor of claim 8 wherein the core (11) is a non-vertical core (11).
10. The nuclear reactor of claim 9 wherein the control rod drive mechanism comprises a housing assembly including a pressure shell (8) and a guide tube,
the pressure shell (8), the guide pipe and the reactor vessel (10) where the reactor core (11) is located form a pressure boundary of the reactor coolant together, so that the reactor coolant is in a sealed and controllable state.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210907383.5A CN115148381A (en) | 2022-07-29 | 2022-07-29 | Control rod driving mechanism and nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210907383.5A CN115148381A (en) | 2022-07-29 | 2022-07-29 | Control rod driving mechanism and nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN115148381A true CN115148381A (en) | 2022-10-04 |
Family
ID=83413230
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202210907383.5A Pending CN115148381A (en) | 2022-07-29 | 2022-07-29 | Control rod driving mechanism and nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN115148381A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115841881A (en) * | 2022-11-30 | 2023-03-24 | 中国原子能科学研究院 | Reactor control rod drive mechanism |
-
2022
- 2022-07-29 CN CN202210907383.5A patent/CN115148381A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115841881A (en) * | 2022-11-30 | 2023-03-24 | 中国原子能科学研究院 | Reactor control rod drive mechanism |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN115148381A (en) | Control rod driving mechanism and nuclear reactor | |
| EA029753B1 (en) | Drive of an emergency safety rod | |
| CN101159172B (en) | Non-passive safety driving mechanism applied to high temperature gas cooled reactor absorption ball shut-down system | |
| CN102255092A (en) | Fuel cell, and method and device for controlling gas supply pressure stability of fuel cell | |
| CN111933314B (en) | Passive shutdown device for nuclear reactor | |
| CN106531235A (en) | Compact type reactive control mechanism for in-situ movement | |
| CN104051029A (en) | Modularized control rod driving system and method for horizontal reactor core structure | |
| CN210344194U (en) | Electric cylinder lifting structure using small servo motor | |
| CN104400216A (en) | Multi-station tin feeding mechanism | |
| CN204262586U (en) | A kind of multistation Song Xi mechanism | |
| RU52243U1 (en) | SERVO ACTUATOR OF AUTOMATIC AND MANUAL CONTROL OF MOVEMENT OF ABSORBING ROD AND EMERGENCY PROTECTION OF ATOMIC REACTOR TYPE RBMK | |
| CN103791001A (en) | Mechanical brake for azimuth axis system | |
| US4587084A (en) | Control rod drive | |
| CN114530981A (en) | Linear push-out motor assembly | |
| CN117577355A (en) | Nuclear reactor driving mechanism | |
| CN203900979U (en) | Numerical control machine tool ball screw displacement resistant device | |
| CN217444075U (en) | Reactor control rod drive mechanism | |
| GB1193060A (en) | Backup Control Rod System. | |
| CN114188047B (en) | Reactivity control device | |
| JPH1130683A (en) | Nuclear reactor control rod driving device | |
| CN101888140A (en) | Reduction gearbox of motor | |
| CN109585040B (en) | Safety bar driving mechanism for small research reactor | |
| CN115188504A (en) | Driving mechanism and nuclear reactor | |
| CN213401460U (en) | Waveguide duplexer of coupler | |
| CN212225423U (en) | Electric fuel pump |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination |