CN110767328A - Device and method for driving shutdown control rod in overturning state of floating nuclear power station - Google Patents
Device and method for driving shutdown control rod in overturning state of floating nuclear power station Download PDFInfo
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- CN110767328A CN110767328A CN201911052308.XA CN201911052308A CN110767328A CN 110767328 A CN110767328 A CN 110767328A CN 201911052308 A CN201911052308 A CN 201911052308A CN 110767328 A CN110767328 A CN 110767328A
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- 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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/12—Means for moving control elements to desired position
- G21C7/16—Hydraulic or pneumatic drive
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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
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Abstract
The invention relates to a device and a method for driving a shutdown control rod in an overturning state of a floating nuclear power station, which are characterized by comprising a slide rail bracket, a pressure plate, a cylinder and a cylinder driving system; the containment vessel is fixed by a support frame, the slide rail bracket is connected with a pressure plate in a sliding manner through a sliding block, a plurality of through holes for movably inserting control rods are formed in the pressure plate, and each control rod penetrates through the corresponding through hole and extends into the containment vessel; the control rods are positioned between the pressure plate and the top of the support frame, each control rod is provided with a limit pin, and each control rod is connected with a conventional control rod driving device; the top of the sliding block is fixedly connected with the output end of the air cylinder, and the input end of the air cylinder is connected with the air cylinder driving system.
Description
Technical Field
The invention relates to a reactor shutdown control rod driving device and method in a floating nuclear power station overturning state, and belongs to the technical field of passive reactor shutdown of marine floating nuclear power stations.
Background
The conventional active shutdown system of the reactor inserts the control rods into the reactor core by using the control rod driving device when the reactor is in an over-design benchmark accident, so that the safe shutdown under the working condition of a serious accident can be realized. Modern reactor control has designed the shutdown system to have a passive shutdown function, in which, when a conventional active shutdown system loses power, control rods can fall down by their own weight to be inserted into the core of the reactor below, thereby realizing passive shutdown.
The floating nuclear power station at sea floats on the sea, and if the floating nuclear power station overturns due to special conditions, the reactor core is positioned above the control rod and is opposite to the direction of gravity. If the reactor system is still supplied with power, the control rod driving device can be used for inserting the control rod into the reactor core to realize shutdown. If the reactor system loses power supply at the moment, because the gravity points to the direction opposite to the reactor core at the moment, the control rods cannot realize the function of passively inserting into the reactor core by means of the gravity, and the original passive shutdown function is failed.
Disclosure of Invention
In view of the above problems, an object of the present invention is to provide a shutdown control rod driving apparatus and method in a submerged state of a floating nuclear power plant, which can still smoothly insert control rods into a core in an extreme case of a power loss and an overturn of a marine floating nuclear power plant.
In order to achieve the purpose, the invention adopts the following technical scheme: the shutdown control rod driving device in the overturning state of the floating nuclear power station is characterized by comprising a slide rail bracket, a pressure plate, a cylinder and a cylinder driving system; the slide rail bracket is fixedly arranged on one side of a containment vessel with a reactor core, the containment vessel is fixed by a support frame, the slide rail bracket is connected with the pressure plate in a sliding manner through a sliding block, a plurality of through holes are formed in the pressure plate, and each control rod penetrates through the corresponding through hole and extends into the containment vessel; the control rods are positioned between the pressure plate and the top of the support frame, each control rod is provided with a limiting pin, each control rod is connected with a conventional control rod driving device, and the conventional control rod driving devices are used for controlling the control rods to be inserted into or pulled out of a reactor core of the containment vessel when the floating nuclear power plant is in a working state; the top of the sliding block is fixedly connected with the output end of the air cylinder, the input end of the air cylinder is connected with the air cylinder driving system, and the air cylinder driving system is used for controlling the pressure plate to move along the slide rail bracket through the driving air cylinder when the floating nuclear power station is in an overturning state with upside-down positions, so that the control rod is controlled to be inserted into the reactor core of the containment vessel.
Preferably, the cylinder comprises a cylinder body, a drive piston and a drive piston rod; the driving piston is movably inserted into the cylinder body, the bottom of the driving piston is fixedly connected with one end of the driving piston rod, and the other end of the driving piston rod penetrates through the bottom of the cylinder body and is fixedly connected with the top of the sliding block; the upper part and the lower part of the cylinder body are both provided with a stopper; the driving piston divides the cylinder body into a cavity A and a cavity B, the cavities are positioned between the top and the upper position of the cylinder body and between the bottom and the lower position of the cylinder body, and the cylinder body is provided with openings for connecting pipelines of the cylinder driving system.
Preferably, the cylinder driving system comprises a two-position three-way electromagnetic directional valve and a driving gas tank, wherein the two-position three-way electromagnetic directional valve comprises a valve body, an electromagnetic switch, a slide valve core assembly, a return spring and a return spring limiter; the electromagnetic switch is arranged on one side of the valve body, the spool assembly and the reset spring are arranged in the valve body, a moving iron core of the electromagnetic switch is fixedly connected with one end of the spool assembly, the other end of the spool assembly is fixedly connected with one end of the reset spring, and the other end of the reset spring is fixedly connected with the valve body; the top and the bottom of the inner side of the valve body are both provided with the return spring limiters for limiting the return spring; the valve body is positioned on two sides of the high-pressure driving gas pipeline, and the bottom of the valve body is provided with an A channel exhaust hole and a B channel exhaust hole; the valve body is positioned between the passage A exhaust hole and the high-pressure driving air pipeline, and the top of the valve body is connected with an opening positioned at the upper part of the cylinder body through a passage A pipeline; the valve body is positioned between the high-pressure driving gas pipeline and the B path exhaust hole, and the top of the valve body is connected with an opening positioned at the lower part of the cylinder body through the B path pipeline.
Preferably, the slide valve core assembly is formed by arranging three reversing valve core pistons on one reversing valve core at intervals, and the distance between the three reversing valve core pistons can ensure that corresponding exhaust holes are opened or closed when the two-position three-way electromagnetic reversing valve is in different opening and closing states.
Preferably, the pressure P of the high-pressure air in the driving air tank is:
wherein W is the total weight of the control rod, pressure plate and slide block, f is the total friction, S is the area of the drive piston, and V iscIs the volume of the cylinder chamber, VtIs the internal volume of the driving gas tank, VpIs the said A channelThe internal volume of the circuit.
Preferably, the pressure plate is arranged between the top of the containment vessel and the conventional control rod drive device, and the distance between the top of the containment vessel and the conventional control rod drive device is larger than the stroke difference of the control rod in normal operation plus the thickness of the pressure plate; and if the distance between the top of the containment vessel and the conventional control rod driving device is not more than the stroke difference of the control rod in normal operation plus the thickness of the pressure plate, increasing the length of the control rod positioned at the outer part of the containment vessel.
The method for driving the shutdown control rod in the overturning state of the floating nuclear power station is characterized by comprising the following steps:
1) when the floating nuclear power station is in a working state, the conventional active shutdown system of the reactor supplies power normally, the conventional control rod driving device supplies power normally, the cylinder driving system is in a power-on state, the cylinder driving system controls the pressure plate to be positioned at a standby position through the driving cylinder, and the conventional control rod driving device controls the control rod to be inserted into or pulled out of the reactor core of the containment vessel; 2) when the floating nuclear power station is in an overturning state with upside down positions, if the power supply of a conventional active shutdown system of the reactor is normal, the power supply of a conventional control rod driving device is normal, a cylinder driving system is in a power-on state, the cylinder driving system controls a pressure plate to be positioned at a standby position through a driving cylinder, and the control rod driving device controls a control rod to be inserted into a reactor core of a containment vessel to realize shutdown; 3) when the floating nuclear power station is in an overturning state with upside down positions, if the conventional active shutdown system of the reactor is powered off, the conventional control rod driving device fails, the cylinder driving system is in a power-off state, and the cylinder driving system drives the cylinder to control the control rod to be inserted into the reactor core of the containment vessel through the slide block and the pressure plate, so that the controllable shutdown is realized.
Preferably, the specific process of step 1) is as follows: 1.1) when the floating nuclear power station is in a normal working state, the conventional active shutdown system of the reactor supplies power normally, and the conventional control rod driving device supplies power normally; 1.2) the electromagnetic switch is electrified, the slide valve core assembly is positioned at the electromagnetic switch side of the valve body, the vent hole of the passage A is opened, the vent hole of the passage B is closed, the high-pressure driving air pipeline is communicated with the passage B pipeline, and high-pressure air from the driving air tank enters a chamber B of the cylinder body through the high-pressure driving air pipeline and the passage B pipeline; meanwhile, gas in the cavity of the cylinder body A is released, the return spring is in a stretching state at the moment, the piston is driven to move to the position of the limiter on the upper part of the cylinder body, and the pressure plate is located at a standby position; 1.3) conventional control rod drive controls control rod insertion or withdrawal into the reactor core of the containment vessel.
Preferably, the specific process of step 2) is as follows: 2.1) when the floating nuclear power station is in an overturning state with upside down positions, if the reactor is not powered off, the conventional active shutdown system of the reactor supplies power normally, and the conventional control rod driving device supplies power normally; 2.2) the electromagnetic switch is electrified, the slide valve core assembly is positioned at the electromagnetic switch side of the valve body, the vent hole of the passage A is opened, the vent hole of the passage B is closed, the high-pressure driving air pipeline is communicated with the passage B pipeline, and high-pressure air from the driving air tank enters the chamber B of the cylinder body through the high-pressure driving air pipeline and the passage B pipeline; meanwhile, gas in the cavity of the cylinder body A is released, the return spring is in a stretching state at the moment, the piston is driven to move to the position of the limiter on the upper part of the cylinder body, and the pressure plate is located at a standby position; 2.3) conventional control rod drive controls control rod insertion or withdrawal into the reactor core of the containment vessel.
Preferably, the specific process of step 3) is as follows: 3.1) when the floating nuclear power station is in an overturning state with upside down positions, if the conventional active shutdown system of the reactor is powered off, the conventional control rod driving device fails; 3.2) the electromagnetic switch is powered off, the slide valve core assembly moves to the other side of the valve body under the action of the reset spring until the exhaust hole of the passage A is closed and the exhaust hole of the passage B is opened, the passage A pipeline is communicated with the high-pressure driving air pipeline, and high-pressure air from the driving air tank enters a chamber A of the cylinder body through the high-pressure driving air pipeline and the passage A pipeline; meanwhile, gas in the cavity B of the cylinder body is released, the reset spring is in a reset state at the moment, the driving piston moves to the position of the limiter at the lower part of the cylinder body, and therefore the control rod is controlled to be inserted into the reactor core of the containment vessel sequentially through the driving piston rod, the sliding block and the pressure plate, and controllable shutdown is achieved.
Due to the adoption of the technical scheme, the invention has the following advantages: the invention is provided with the sliding block, the pressure plate, the cylinder and the cylinder driving system, the cylinder driving system depends on the stored compressed air as the driving mechanism, when the offshore floating nuclear power station is in the overturn state with upside down positions, the control rod can be smoothly inserted into the reactor core above the control rod, and the control rod can not continuously fall from the through hole on the pressure plate because the control rod is provided with the limit pin, but the control rod is pushed by the pressure plate to overcome the gravity and is upwards inserted into the reactor, thereby realizing the passive shutdown, and being widely applied to the technical field of the passive shutdown of the offshore floating nuclear power station.
Drawings
FIG. 1 is a schematic view of the overall structure of a driving apparatus of the present invention;
FIG. 2 is a plan view of a part of the structure of the driving apparatus of the present invention;
FIG. 3 is a schematic structural diagram of a two-position three-way electromagnetic directional valve in the driving device of the present invention;
fig. 4 is a schematic view of the driving apparatus of the present invention when the floating nuclear power plant is in an overturned state with the upper and lower positions reversed.
Detailed Description
The present invention is described in detail below with reference to the attached drawings. It is to be understood, however, that the drawings are provided solely for the purposes of promoting an understanding of the invention and that they are not to be construed as limiting the invention. In the description of the present invention, it is to be understood that the terms "first," "second," and the like are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
As shown in fig. 1 and fig. 2, the shutdown control rod driving device in the overturning state of the floating nuclear power plant provided by the invention comprises a slide rail bracket 1, a slide block 2, a pressure plate 3, an air cylinder 4 and an air cylinder driving system 5.
The slide rail bracket 1 is fixedly provided on the containment vessel 6 side where the reactor core 51 is placed, and the containment vessel 6 is fixed by a support frame 7 using a frame structure. The slide rail bracket 1 is connected with a slide block 2 in a sliding mode, one side of the slide block 2 is fixedly connected with a pressure plate 3, a plurality of through holes 11 used for movably inserting control rods 8 are formed in the pressure plate 3 in an array mode, and each control rod 8 penetrates through the corresponding through hole 11 and extends into the containment vessel 6. And a limiting pin 81 is arranged on each control rod 8 between the pressure plate 3 and the top of the support frame 7, each control rod 8 is connected with an external conventional control rod driving device, and the conventional control rod driving device is used for controlling the control rods 8 to be inserted into or pulled out of the reactor core 51 of the containment vessel 6 when the floating nuclear power plant is in a working state. The top of the sliding block 2 is fixedly connected with the output end of the cylinder 4, the input end of the cylinder 4 is connected with the cylinder driving system 5, and the cylinder driving system 5 is used for controlling the sliding block 2 to move along the sliding rail bracket 1 through driving the cylinder 4 when the floating nuclear power station is in an overturn state with upside-down positions, so that the pressure plate 3 moves along the sliding rail bracket 1, and the control rod 8 is further controlled to be inserted into the reactor core 51 of the containment vessel 6, and controllable shutdown is realized.
In a preferred embodiment, the cylinder 4 comprises a cylinder 41, a drive piston 42 and a drive piston rod 43. A driving piston 42 is movably inserted in the cylinder 41. The bottom of the driving piston 42 is fixedly connected with one end of a driving piston rod 43, and the other end of the driving piston rod 43 penetrates through the bottom of the cylinder 41 and is fixedly connected with the top of the sliding block 2. The cylinder 41 is provided at both upper and lower portions thereof with stoppers 44. The driving piston 42 divides the cylinder 41 into two parts, namely a chamber a and a chamber B, and is located between the top of the cylinder 41 and the upper stopper 44 and between the bottom of the cylinder 41 and the lower stopper 44, and the cylinder 41 is provided with openings for connecting pipelines of the cylinder driving system 5. When the chamber A is full of air, the chamber B is empty, and the driving piston 42 is positioned at the upper limit position; when chamber B is full, chamber a is empty and the drive piston 42 is at the lower limit.
In a preferred embodiment, as shown in fig. 1 and 3, the cylinder driving system 5 comprises a two-position three-way electromagnetic directional valve 51, a driving gas tank 52 and a vent line, wherein the two-position three-way electromagnetic directional valve 51 comprises a valve body 511, an electromagnetic switch 512, a spool assembly 513, a return spring 514 and a return spring stopper 515, the vent line comprises an a-path line 531, a B-path line 532 and a high-pressure driving gas line 533, the spool assembly 513 is formed by arranging three spool pistons 517 on a spool 516 at intervals, and the intervals between the three spool pistons 517 are just enough to ensure that the corresponding vent holes are opened or closed when the two-position three-way electromagnetic directional valve 51 is in different switch states.
An electromagnetic switch 512 is arranged on one side of the valve body 511, a spool assembly 513 and a return spring 514 are arranged in the valve body 511, a moving core of the electromagnetic switch 512 is fixedly connected with one end of the spool assembly 513, the other end of the spool assembly 513 is fixedly connected with one end of the return spring 514, and the other end of the return spring 514 is fixedly connected with the valve body 511. The top and the bottom of the inner side of the valve body 511 are both provided with a return spring stopper 515 for limiting the return spring 514. The bottom center of the valve body 511 is connected to a driving air tank 52 containing high-pressure air through a high-pressure driving air line 533. Located on both sides of the high pressure driving air pipe 533, and the bottom of the valve body 511 is opened with an a-path exhaust hole 54 and a B-path exhaust hole 55. Between the a-path exhaust hole 54 and the high-pressure driving air line 533, the top of the valve body 511 is connected to the opening at the upper part of the cylinder 41 through the a-path line 531; between the high-pressure drive gas line 533 and the B-path exhaust hole 55, the top of the valve body 511 is connected to an opening at the lower portion of the cylinder 41 through the B-path line 532. The two-position three-way electromagnetic reversing valve 51 is connected with the conventional reactor active shutdown system by one circuit, namely, the two-position three-way electromagnetic reversing valve 51 cannot be powered off when the conventional reactor active shutdown system is powered on.
In a preferred embodiment, the high pressure gas driving the gas tank 52 is such that when the containment vessel 6 is in an upside down, overturning condition, the chamber a of the cylinder 41 provides sufficient pressure to overcome the gravity and static friction of the control rods 8, the pressure plate 3 and the slide 2 to insert the control rods 8 into the reactor core 51. The pressure of the high pressure air in the drive air tank 52 may be determined using the following algorithm:
assuming that high-pressure air is ideal gas, the inflation process of the cylinder 4 is an isothermal process, the total weight of the control rod 8, the pressure plate 3 and the slide block 2 is set as W, the total friction force is set as f, the area of the driving piston 42 is set as S, and the volume of the cavity of the cylinder 41 is set as VcThe inner volume of the driving gas tank 52 is VtThe internal volume of the A-channel pipe 531 is VpThe pressure P of the high-pressure air should satisfy the following equationFormula (II):
in a preferred embodiment, the platen 3 is disposed between the top of the containment vessel 6 and a conventional control rod drive. The distance between the top of the containment vessel 6 and the conventional control rod drive should be greater than the stroke difference of the control rod 8 during normal operation (i.e., the stroke difference of the control rod 8 when the control rod is fully inserted into the reactor core 51 and when the control rod is pulled out of the reactor core 51) plus the thickness of the pressure plate 3 to ensure that sufficient stroke space is not blocked by the pressure plate 3 when the conventional control rod drive lifts the control rod 8. If the distance between the top of the containment vessel 6 and the conventional control rod drive is not greater than the stroke difference of the control rod 8 in normal operation plus the thickness of the pressure plate 3, the length of the control rod 8 outside the containment vessel 6 can be increased. The standby position of the platen 3 (i.e., the position where the chamber B of the cylinder 41 is filled with gas and the chamber a of the cylinder 41 is evacuated so that the platen 3 does not press the control rod 8 into the reactor) should ensure that sufficient stroke space is not blocked by the platen 3 when the control rod 8 is lifted by a conventional control rod drive.
In a preferred embodiment, the position of the limit pin 81 on each control rod 8 is such that the conventional control rod drive lifts the control rod 8 with sufficient travel space that is not blocked by the pressure plate 3. In addition, the limit pin 81 of the control rod 8 is not lifted to the standby position of the platen 3, i.e., does not collide with the platen 3, in the stroke range driven by the conventional control rod driving apparatus.
Based on the shutdown control rod driving device in the overturning state of the floating nuclear power station, the invention also provides a shutdown control rod driving method in the overturning state of the floating nuclear power station, which comprises the following steps:
1) when the floating nuclear power station is in a working state, the conventional active shutdown system of the reactor supplies power normally, the conventional control rod driving device supplies power normally, the cylinder driving system 5 is in a power-on state, the cylinder driving system 5 controls the pressure plate 3 to be located at a standby position through the driving cylinder 4, and the control rod 8 can be controlled to be inserted into or pulled out of the reactor core 51 of the containment vessel 6 by using the original conventional control rod driving device, specifically:
1.1) when the floating nuclear power station is in a normal working state, the reactor normal active shutdown system supplies power normally, the normal control rod driving device supplies power normally, and therefore the electromagnetic switch 512 in the two-position three-way electromagnetic directional valve 51 is in a power-on state.
1.2) the electromagnetic switch 512 is energized, the spool assembly 513 is positioned on the electromagnetic switch 512 side of the valve body 511, the a-path exhaust hole 54 is opened, the B-path exhaust hole 55 is closed, the high-pressure drive air line 533 and the B-path line 532 are communicated, and the high-pressure air from the drive air tank 52 enters the B chamber of the cylinder 51 through the high-pressure drive air line 533 and the B-path line 532. At the same time, the gas in the chamber of the cylinder 41A is released, and at this time, the return spring 514 is in a stretched state, the driving piston 42 moves to the stopper 44 at the upper part of the cylinder 41, i.e., the upper limit, and the pressure plate 3 is located at the standby position, wherein the pressure in the chamber of the cylinder 41B is enough to overcome the gravity of the pressure plate 3 and the control rod 8, so that the pressure plate does not fall under the action of gravity.
1.3) the control rods 8 can now be controlled to be inserted into or withdrawn from the reactor core 51 of the containment vessel 6 by means of the existing conventional control rod drive.
2) When the floating nuclear power station is in an overturn state with upside down positions and needs emergency shutdown, if the conventional active shutdown system of the reactor supplies power normally, the conventional control rod driving device supplies power normally, the cylinder driving system 5 is in a power-on state, the cylinder driving system 5 controls the pressure plate 3 to be located at a standby position through the driving cylinder 4, and at the moment, the control rod 8 can be controlled to be inserted into the reactor core 51 of the containment vessel 6 by utilizing the original conventional control rod driving device to realize shutdown, which specifically comprises the following steps:
2.1) as shown in fig. 4, when the floating nuclear power plant is in an overturning state with upside down positions, if the reactor is not powered off, the power supply of the conventional active reactor shutdown system of the reactor is normal, the power supply of the conventional control rod driving device is normal, and the electromagnetic switch 512 in the two-position three-way electromagnetic directional valve 51 is in a power-on state.
2.2) the electromagnetic switch 512 is energized, the spool assembly 513 is positioned on the electromagnetic switch 512 side of the valve body 511, the a-path exhaust hole 54 is opened, the B-path exhaust hole 55 is closed, the high-pressure drive air line 533 and the B-path line 532 are communicated, and the high-pressure air from the drive air tank 52 enters the B chamber of the cylinder 51 through the high-pressure drive air line 533 and the B-path line 532. At the same time, the gas in the chamber of the cylinder 41A is released, and at this time, the return spring 514 is in a stretched state, the driving piston 42 moves to the stopper 44 at the upper part of the cylinder 41, i.e., the upper limit, and the pressure plate 3 is located at the standby position, wherein the pressure in the chamber of the cylinder 41B is enough to overcome the gravity of the pressure plate 3 and the control rod 8, so that the pressure plate does not fall under the action of gravity.
2.3) at the moment, the control rod 8 can be controlled to be inserted into the reactor core 51 of the containment vessel 6 by utilizing the original conventional control rod driving device, so that shutdown is realized.
3) When the floating nuclear power station is in an overturn state with upside down positions and needs emergency shutdown, if the conventional active shutdown system of the reactor is powered off at the moment, the conventional control rod driving device fails, the cylinder driving system 5 is in a power-off state, the cylinder driving system 5 controls the control rod 8 to be inserted into the reactor core 51 of the containment vessel 6 through the driving cylinder 4 by the slide block 2 and the pressure plate 3, so that controllable shutdown is realized, and the method specifically comprises the following steps:
3.1) when the floating nuclear power station is in an overturn state with upside down positions, if the reactor normal active shutdown system is powered off, the normal control rod driving device fails, and at the moment, the electromagnetic switch 512 in the two-position three-way electromagnetic directional valve 51 is in a power-off state.
3.2) the electromagnetic switch 612 is powered off, the spool assembly 513 moves towards the other side of the valve body 511 under the action of the return spring 514 until the a-path exhaust hole 54 is closed, the B-path exhaust hole 55 is opened, the a-path pipeline 531 is communicated with the high-pressure driving air pipeline 533, and the high-pressure air from the driving air tank 52 enters the a chamber of the cylinder 41 through the high-pressure driving air pipeline 533 and the a-path pipeline 531. Meanwhile, the gas in the cavity of the cylinder 41B is released, at this time, the return spring 514 is in a return state, the driving piston 42 moves to the stopper 44 at the lower part of the cylinder 41, namely, the lower limit position, so that the control rod 8 is controlled to be inserted into the reactor core 51 of the containment vessel 6 through the driving piston rod 43, the slider 2 and the pressure plate 3 in sequence, and the controllable shutdown is realized.
The above embodiments are only used for illustrating the present invention, and the structure, connection mode, manufacturing process, etc. of the components may be changed, and all equivalent changes and modifications performed on the basis of the technical solution of the present invention should not be excluded from the protection scope of the present invention.
Claims (10)
1. The shutdown control rod driving device in the overturning state of the floating nuclear power station is characterized by comprising a slide rail bracket, a pressure plate, a cylinder and a cylinder driving system;
the slide rail bracket is fixedly arranged on one side of a containment vessel with a reactor core, the containment vessel is fixed by a support frame, the slide rail bracket is connected with the pressure plate in a sliding manner through a sliding block, a plurality of through holes are formed in the pressure plate, and each control rod penetrates through the corresponding through hole and extends into the containment vessel; the control rods are positioned between the pressure plate and the top of the support frame, each control rod is provided with a limiting pin, each control rod is connected with a conventional control rod driving device, and the conventional control rod driving devices are used for controlling the control rods to be inserted into or pulled out of a reactor core of the containment vessel when the floating nuclear power plant is in a working state;
the top of the sliding block is fixedly connected with the output end of the air cylinder, the input end of the air cylinder is connected with the air cylinder driving system, and the air cylinder driving system is used for controlling the pressure plate to move along the slide rail bracket through the driving air cylinder when the floating nuclear power station is in an overturning state with upside-down positions, so that the control rod is controlled to be inserted into the reactor core of the containment vessel.
2. The shutdown control rod drive device in an overturning state of a floating nuclear power plant as set forth in claim 1, wherein the cylinder comprises a cylinder body, a drive piston and a drive piston rod;
the driving piston is movably inserted into the cylinder body, the bottom of the driving piston is fixedly connected with one end of the driving piston rod, and the other end of the driving piston rod penetrates through the bottom of the cylinder body and is fixedly connected with the top of the sliding block; the upper part and the lower part of the cylinder body are both provided with a stopper;
the driving piston divides the cylinder body into a cavity A and a cavity B, the cavities are positioned between the top and the upper position of the cylinder body and between the bottom and the lower position of the cylinder body, and the cylinder body is provided with openings for connecting pipelines of the cylinder driving system.
3. The control rod drive device for a shutdown control rod in an overturning state of a floating nuclear power plant as claimed in claim 2, wherein the cylinder drive system comprises a two-position three-way electromagnetic directional valve and a drive gas tank, wherein the two-position three-way electromagnetic directional valve comprises a valve body, an electromagnetic switch, a spool assembly, a return spring and a return spring retainer;
the electromagnetic switch is arranged on one side of the valve body, the spool assembly and the reset spring are arranged in the valve body, a moving iron core of the electromagnetic switch is fixedly connected with one end of the spool assembly, the other end of the spool assembly is fixedly connected with one end of the reset spring, and the other end of the reset spring is fixedly connected with the valve body; the top and the bottom of the inner side of the valve body are both provided with the return spring limiters for limiting the return spring;
the valve body is positioned on two sides of the high-pressure driving gas pipeline, and the bottom of the valve body is provided with an A channel exhaust hole and a B channel exhaust hole; the valve body is positioned between the passage A exhaust hole and the high-pressure driving air pipeline, and the top of the valve body is connected with an opening positioned at the upper part of the cylinder body through a passage A pipeline; the valve body is positioned between the high-pressure driving gas pipeline and the B path exhaust hole, and the top of the valve body is connected with an opening positioned at the lower part of the cylinder body through the B path pipeline.
4. The shutdown control rod driving device in the overturning state of the floating nuclear power plant as claimed in claim 3, wherein the spool assembly is formed by arranging three reversing spool pistons on one reversing spool at intervals, and the distance between the three reversing spool pistons can ensure that the corresponding exhaust holes are opened or closed when the two-position three-way electromagnetic reversing valve is in different switching states.
5. The shutdown control rod drive device in an overturning state of a floating nuclear power plant as set forth in claim 3, wherein the pressure P of the high-pressure air in the drive air tank is:
wherein W is the total weight of the control rod, pressure plate and slide block, f is the total friction, S is the area of the drive piston, and V iscIs the volume of the cylinder chamber, VtIs the internal volume of the driving gas tank, VpIs the internal volume of the a-pass line.
6. A shutdown control rod drive apparatus in a capsizing condition of a floating nuclear power plant as set forth in any one of claims 1 to 5, characterized in that the pressure plate is disposed between the top of the containment vessel and the conventional control rod drive apparatus, and the distance between the top of the containment vessel and the conventional control rod drive apparatus is greater than the stroke difference of the control rod in normal operation plus the thickness of the pressure plate;
and if the distance between the top of the containment vessel and the conventional control rod driving device is not more than the stroke difference of the control rod in normal operation plus the thickness of the pressure plate, increasing the length of the control rod positioned at the outer part of the containment vessel.
7. The method for driving the shutdown control rod in the overturning state of the floating nuclear power station is characterized by comprising the following steps:
1) when the floating nuclear power station is in a working state, the conventional active shutdown system of the reactor supplies power normally, the conventional control rod driving device supplies power normally, the cylinder driving system is in a power-on state, the cylinder driving system controls the pressure plate to be positioned at a standby position through the driving cylinder, and the conventional control rod driving device controls the control rod to be inserted into or pulled out of the reactor core of the containment vessel;
2) when the floating nuclear power station is in an overturning state with upside down positions, if the power supply of a conventional active shutdown system of the reactor is normal, the power supply of a conventional control rod driving device is normal, a cylinder driving system is in a power-on state, the cylinder driving system controls a pressure plate to be positioned at a standby position through a driving cylinder, and the control rod driving device controls a control rod to be inserted into a reactor core of a containment vessel to realize shutdown;
3) when the floating nuclear power station is in an overturning state with upside down positions, if the conventional active shutdown system of the reactor is powered off, the conventional control rod driving device fails, the cylinder driving system is in a power-off state, and the cylinder driving system drives the cylinder to control the control rod to be inserted into the reactor core of the containment vessel through the slide block and the pressure plate, so that the controllable shutdown is realized.
8. The method for driving the shutdown control rod in the overturning state of the floating nuclear power plant as claimed in claim 7, wherein the specific process of the step 1) is as follows:
1.1) when the floating nuclear power station is in a normal working state, the conventional active shutdown system of the reactor supplies power normally, and the conventional control rod driving device supplies power normally;
1.2) the electromagnetic switch is electrified, the slide valve core assembly is positioned at the electromagnetic switch side of the valve body, the vent hole of the passage A is opened, the vent hole of the passage B is closed, the high-pressure driving air pipeline is communicated with the passage B pipeline, and high-pressure air from the driving air tank enters a chamber B of the cylinder body through the high-pressure driving air pipeline and the passage B pipeline; meanwhile, gas in the cavity of the cylinder body A is released, the return spring is in a stretching state at the moment, the piston is driven to move to the position of the limiter on the upper part of the cylinder body, and the pressure plate is located at a standby position;
1.3) conventional control rod drive controls control rod insertion or withdrawal into the reactor core of the containment vessel.
9. The method for driving the shutdown control rod in the overturning state of the floating nuclear power plant as claimed in claim 8, wherein the specific process of the step 2) is as follows:
2.1) when the floating nuclear power station is in an overturning state with upside down positions, if the reactor is not powered off, the conventional active shutdown system of the reactor supplies power normally, and the conventional control rod driving device supplies power normally;
2.2) the electromagnetic switch is electrified, the slide valve core assembly is positioned at the electromagnetic switch side of the valve body, the vent hole of the passage A is opened, the vent hole of the passage B is closed, the high-pressure driving air pipeline is communicated with the passage B pipeline, and high-pressure air from the driving air tank enters the chamber B of the cylinder body through the high-pressure driving air pipeline and the passage B pipeline; meanwhile, gas in the cavity of the cylinder body A is released, the return spring is in a stretching state at the moment, the piston is driven to move to the position of the limiter on the upper part of the cylinder body, and the pressure plate is located at a standby position;
2.3) conventional control rod drive controls control rod insertion or withdrawal into the reactor core of the containment vessel.
10. The method for driving the shutdown control rod in the overturning state of the floating nuclear power plant as claimed in claim 7, wherein the specific process of the step 3) is as follows:
3.1) when the floating nuclear power station is in an overturning state with upside down positions, if the conventional active shutdown system of the reactor is powered off, the conventional control rod driving device fails;
3.2) the electromagnetic switch is powered off, the slide valve core assembly moves to the other side of the valve body under the action of the reset spring until the exhaust hole of the passage A is closed and the exhaust hole of the passage B is opened, the passage A pipeline is communicated with the high-pressure driving air pipeline, and high-pressure air from the driving air tank enters a chamber A of the cylinder body through the high-pressure driving air pipeline and the passage A pipeline; meanwhile, gas in the cavity B of the cylinder body is released, the reset spring is in a reset state at the moment, the driving piston moves to the position of the limiter at the lower part of the cylinder body, and therefore the control rod is controlled to be inserted into the reactor core of the containment vessel sequentially through the driving piston rod, the sliding block and the pressure plate, and controllable shutdown is achieved.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN113744898A (en) * | 2021-08-03 | 2021-12-03 | 西安交通大学 | Passive shutdown device and control method thereof |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4110157A (en) * | 1976-11-10 | 1978-08-29 | The Babcock & Wilcox Co. | Industrial technique |
| JPS62137585A (en) * | 1985-12-11 | 1987-06-20 | 株式会社東芝 | Motor control-rod drive mechanism for nuclear power plant |
| JPH09257974A (en) * | 1996-03-22 | 1997-10-03 | Japan Atom Energy Res Inst | Nuclear reactor of moving type |
| CN104051029A (en) * | 2014-07-02 | 2014-09-17 | 中国科学院合肥物质科学研究院 | Modularized control rod driving system and method for horizontal reactor core structure |
| CN105788667A (en) * | 2016-05-06 | 2016-07-20 | 上海核工程研究设计院 | Control rod driving mechanism of floating type reactor |
| CN207250148U (en) * | 2017-07-31 | 2018-04-17 | 清华大学天津高端装备研究院 | Passive reactor shut-off system and nuclear reactor |
| 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 |
-
2019
- 2019-10-31 CN CN201911052308.XA patent/CN110767328B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4110157A (en) * | 1976-11-10 | 1978-08-29 | The Babcock & Wilcox Co. | Industrial technique |
| JPS62137585A (en) * | 1985-12-11 | 1987-06-20 | 株式会社東芝 | Motor control-rod drive mechanism for nuclear power plant |
| JPH09257974A (en) * | 1996-03-22 | 1997-10-03 | Japan Atom Energy Res Inst | Nuclear reactor of moving type |
| CN104051029A (en) * | 2014-07-02 | 2014-09-17 | 中国科学院合肥物质科学研究院 | Modularized control rod driving system and method for horizontal reactor core structure |
| CN105788667A (en) * | 2016-05-06 | 2016-07-20 | 上海核工程研究设计院 | Control rod driving mechanism of floating type reactor |
| CN207250148U (en) * | 2017-07-31 | 2018-04-17 | 清华大学天津高端装备研究院 | Passive reactor shut-off system and nuclear reactor |
| 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 (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113744898A (en) * | 2021-08-03 | 2021-12-03 | 西安交通大学 | Passive shutdown device and control method thereof |
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