CN116130122A - Automatic power control system for heat pipe cooling reactor - Google Patents
Automatic power control system for heat pipe cooling reactor Download PDFInfo
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- CN116130122A CN116130122A CN202310058367.8A CN202310058367A CN116130122A CN 116130122 A CN116130122 A CN 116130122A CN 202310058367 A CN202310058367 A CN 202310058367A CN 116130122 A CN116130122 A CN 116130122A
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- heat pipe
- control rod
- reactor
- control
- top surface
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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
- G21C7/10—Construction of control elements
- G21C7/11—Deformable control elements, e.g. flexible, telescopic, articulated
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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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- 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
- G21C15/24—Promoting flow of the coolant
- G21C15/257—Promoting flow of the coolant using heat-pipes
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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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a power automatic control system for a heat pipe cooling reactor, which comprises the following components: a heat pipe heat exchanger; a reactor core metal matrix is arranged in the reflecting layer and the shielding, a plurality of fuel rods are arranged in the reactor core metal matrix, a heat pipe heat exchanger is arranged above the reactor core, a plurality of heat pipes are arranged between the heat pipe heat exchanger and the reactor core as heat exchange elements, and a central hole is formed in the top surface of the reactor core metal matrix; the control part comprises a control rod, a containing cavity is formed in the bottom surface of the heat pipe heat exchanger, a protection shell is fixedly connected in the containing cavity, the top of the control rod is arranged in the protection shell, the bottom of the control rod penetrates through the core base metal body and is located in the central hole, an upper limiting part is arranged at the top of the control rod, and a lower limiting part is arranged at the bottom of the control rod. The invention can realize the automatic control of the power of the heat pipe cooling reactor, the automatic shutdown of the reactor under the accident condition and the adjustment of the operating temperature of the reactor, thereby improving the safety and the reliability of the heat pipe cooling nuclear reactor system.
Description
Technical Field
The invention relates to the technical field of nuclear reactor safety, in particular to a power automatic control system for a heat pipe cooling reactor.
Background
The heat pipe cooling reactor has the performance advantages of simple operation characteristic, small volume and weight, modularization, easy expansion and the like, and can be used for supplying energy for equipment such as ocean unmanned underwater vehicles, space vehicles and the like in complex environments such as deep space, deep sea and the like. The power control of a small nuclear power system used in a special unmanned environment is greatly different from that of a nuclear power station, and how to realize unmanned autonomous control of a reactor is one of main problems. Moreover, due to the special application scene of the heat pipe pile, a power control method under the movement condition of the reactor needs to be considered, and particularly when the reactor has attitude change in the running process, the traditional gravity-based passive control and shutdown strategy is not applicable any more, and a novel control system needs to be developed for carrying out power control, regulation and emergency shutdown of the heat pipe pile.
Disclosure of Invention
The invention aims to provide a power automatic control system for a heat pipe cooling reactor, which solves the problems in the prior art, and can realize the automatic control of the power of the heat pipe cooling reactor, the automatic shutdown of the reactor under the accident condition and the temperature regulation of the reactor operation without depending on the action of gravity, thereby improving the safety and the reliability of the heat pipe cooling nuclear reactor system.
In order to achieve the above object, the present invention provides the following solutions: the invention provides an automatic power control system for a heat pipe cooling reactor, which comprises the following components:
a heat pipe heat exchanger;
the reactor core comprises a reflecting layer and a shielding, a core metal matrix is arranged in the reflecting layer and the shielding, a plurality of fuel rods are arranged in the core metal matrix, a heat pipe heat exchanger is arranged above the reactor core, a heat exchange element is arranged between the heat pipe heat exchanger and the reactor core, and a central hole is formed in the top surface of the core metal matrix;
the control part comprises a control rod, a containing cavity is formed in the bottom surface of the heat pipe heat exchanger, a protection shell is fixedly connected in the containing cavity, the bottom of the protection shell is welded with the top surface of the core metal matrix, the top of the control rod is arranged in the protection shell, the bottom of the control rod penetrates through the core metal matrix and is located in the central hole, an upper limiting part is arranged at the top of the control rod, and a lower limiting part is arranged at the bottom of the control rod.
Preferably, the upper limiting part comprises a compression spring, the top surface of the compression spring is fixedly connected with the top surface of the inner cavity of the protection shell, the bottom surface of the compression spring is abutted with the top surface of the control rod, and a fixing device is fixedly connected outside the control rod;
the fixing device comprises a fixing ring, wherein the outer wall of the fixing ring is fixedly connected with a sliding ring through a connecting rod, and the outer wall of the sliding ring is in sliding contact with the inner wall of the shell.
Preferably, the lower limiting piece comprises a temperature control spring, an electric adjusting device is fixedly connected to the bottom surface of the inner cavity of the central hole, the output end of the electric adjusting device is fixedly connected with the bottom of the temperature control spring, a limiter is sleeved at the bottom of the control rod, the top surface of the temperature control spring is abutted to the bottom surface of the limiter, and the inner diameter of the temperature control spring is larger than the outer diameter of the control rod;
the bottom surface top surface of stopper sets up to groove structure, just groove structure with control stick bottom butt.
Preferably, the core metal matrix is provided with a cylindrical structure, the central hole is formed in the center of the top surface of the core metal matrix, the top surface of the core metal matrix is circumferentially and equidistantly provided with a plurality of heat pipe holes and fuel holes around the central hole, and a plurality of fuel rods are respectively positioned in a plurality of the fuel holes.
Preferably, the heat exchange element comprises a plurality of high-temperature heat pipes, a condensation section of each high-temperature heat pipe is inserted into the heat pipe exchanger, and an evaporation section of each high-temperature heat pipe penetrates through the reflecting layer and is shielded and inserted into the heat pipe hole.
Preferably, the fuel rod material is uranium dioxide.
Preferably, the operating working medium of the high-temperature heat pipe is sodium.
Preferably, the core metal matrix is 316 stainless steel.
Preferably, the material of the control rod is B 4 And C, the boron content of the control rod is sequentially increased along the bottom-to-top direction of the control rod.
Preferably, the melting temperature of the limiter is 1500K.
The invention discloses the following technical effects:
the technical scheme provides the power automatic control system for the heat pipe cooling reactor, which realizes the functions of automatic power control, automatic accident shutdown and operation temperature regulation of the heat pipe cooling reactor, can solve the difficult problem that the heat pipe reactor is difficult to control in unmanned application scenes such as deep space, deep sea and the like, and can further improve the safety and reliability of the heat pipe cooling nuclear reactor system.
According to the technical scheme, the change characteristic of the spring elastic coefficient along with the temperature is applied to the power control of the nuclear reactor system, and the rapid load following can be realized by matching with the negative feedback effect of the temperature and the thermal expansion of the reactor, so that the system does not depend on manual operation and has higher passive safety characteristic;
according to the technical scheme, the power control of the reactor is realized by means of the acting force of the internal spring, the automatic shutdown is independent of gravity or other external acting forces, the heat pipe stacks can be vertically or transversely arranged, and the operation of the heat pipe stacks is not limited by the installation direction.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings that are needed in the embodiments will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 is a schematic diagram of a power automation control system for a heat pipe cooled reactor according to the present invention;
FIG. 2 is a schematic view of a fixing device according to the present invention;
wherein, 1, compressing the spring; 2. a high temperature heat pipe; 3. a fixing device; 4. a heat pipe heat exchanger; 5. a control rod; 6. a protective housing; 7. a limiter; 8. a temperature control spring; 9. a fuel rod; 10. a reflective layer and a shield; 11. a reactor core; 12. a core metal matrix; 13. an electric adjusting device.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and completely with reference to the accompanying drawings, in which it is apparent that the embodiments described are only some embodiments of the present invention, but not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
In order that the above-recited objects, features and advantages of the present invention will become more readily apparent, a more particular description of the invention will be rendered by reference to the appended drawings and appended detailed description.
Referring to fig. 1-2, the present invention provides an automatic power control system for a heat pipe cooled reactor, comprising:
a heat pipe exchanger 4;
the reactor core 11 comprises a reflecting layer and a shielding 10, a core metal matrix 12 is arranged in the reflecting layer and the shielding 10, a plurality of fuel rods 9 are arranged in the core metal matrix 12, the heat pipe heat exchanger 4 is arranged above the reactor core 11, a heat exchange element is arranged between the heat pipe heat exchanger 4 and the reactor core 11, and a central hole is formed in the top surface of the core metal matrix 12;
the control part, the control part includes control rod 5, and the bottom surface of heat pipe heat exchanger 4 has been seted up and has been held the chamber, holds the intracavity rigid coupling and has been protected casing 6, and the bottom of protection casing 6 is welded with core metal base 12 top surface, and control rod 5 top sets up in protection casing 6, and the bottom of control rod 5 runs through core metal base and is located the center hole, and the top of control rod 5 is provided with the locating part, and the bottom of control rod 5 is provided with the locating part down.
In a further optimized scheme, the upper limiting piece comprises a compression spring 1, the top surface of the compression spring 1 is fixedly connected with the top surface of the inner cavity of the protection shell 6, the bottom surface of the compression spring 1 is abutted with the top surface of the control rod 5, and the fixing device 3 is fixedly connected outside the control rod 5;
the hold-down spring 1 is in a compressed state to provide a force directed toward the core to the control rod 5, and when the provided elastic force is completely released, the control rod 5 can be moved to the bottommost position of the core.
The fixing device 3 comprises a fixing ring, wherein the outer wall of the fixing ring is fixedly connected with a sliding ring through a connecting rod, and the outer wall of the sliding ring is in sliding contact with the inner wall of the shell.
In a further optimized scheme, the lower limiting piece comprises a temperature control spring 8, an electric adjusting device 13 is fixedly connected to the bottom surface of the inner cavity of the central hole, the output end of the electric adjusting device 13 is fixedly connected with the bottom of the temperature control spring 8, a limiter 7 is sleeved at the bottom of the control rod 5, the top surface of the temperature control spring 8 is abutted to the bottom surface of the limiter 7, and the inner diameter of the temperature control spring 8 is larger than the outer diameter of the control rod 5;
the elastic coefficient of the temperature control spring 8 changes along with the change of the temperature of the reactor core, the elastic force of the temperature control spring 8 is reduced when the temperature of the reactor core is increased, the elastic force of the compression spring 1 is unchanged, the control rod 5 moves into the reactor, negative reactivity is introduced, and the power of the reactor is reduced; when the core temperature decreases, the opposite is true.
The bottom surface top surface of the limiter 7 is provided with a groove structure, and the groove structure is abutted with the bottom of the control rod 5.
The electric control device 13 at the bottom of the reactor core can adjust the position of the control rod 5 by compressing or releasing the temperature control spring 8, thereby setting the operating temperature of the heat pipe stack.
Further optimizing scheme, the reactor core metal matrix 12 is arranged to be of a cylindrical structure, the center hole is formed in the center of the top surface of the reactor core metal matrix 12, the top surface of the reactor core metal matrix 12 is provided with a plurality of heat pipe holes and fuel holes at equal intervals around the circumference of the center hole, and a plurality of fuel rods 9 are respectively located in the plurality of fuel holes.
Further optimizing scheme, the heat exchange element includes a plurality of high temperature heat pipes 2, and the condensation section of high temperature heat pipe 2 inserts in the heat pipe heat exchanger 4, and the evaporation section of high temperature heat pipe 2 runs through the reflection stratum and shielding 10 inserts in the heat pipe hole.
The reflective layer and the shield 10 completely encapsulate the core metal matrix 12.
In a further preferred embodiment, the fuel rod 9 is uranium dioxide.
In a further optimized scheme, the operating working medium of the high-temperature heat pipe 2 is sodium.
Further preferably, the core metal matrix 12 is 316 stainless steel.
Further optimizing scheme, the material of the control rod 5 is B 4 C, and the boron content of the control rod 5 increases in sequence from the bottom to the top of the control rod 5. The neutron absorption capacity of the control rod 5 increases from bottom to top. The reactor power control system can assist in temperature negative feedback adjustment, and can realize rapid following of the reactor power along with the change of external load.
In a further preferred embodiment, the melting temperature of the stopper 7 is 1500K.
When the temperature of the reactor core exceeds the melting temperature, the limiter 7 melts, the control rod 5 completely enters the reactor core under the action of the elastic force of the compression spring 1, a large amount of negative reactivity is introduced, and the reactor is stopped.
The temperature control spring 8 can push the control rod 5 to move under the change of elasticity at different core temperatures, so as to control the reactor power; when the temperature of the reactor core exceeds 1500K, the limiter 7 on the control rod 5 is melted, and the compression spring 1 pushes the control rod 5 to be completely inserted into the reactor core, so that the quick shutdown can be realized; the position of the control rod 5 during steady operation can be changed by operating the electric adjustment device 13 to adjust the operating temperature of the reactor. The invention applies the change characteristic of the spring elastic coefficient along with the temperature to the operation control of the nuclear reactor system, does not depend on manual operation and gravity action, realizes the functions of automatic power control, automatic accident shutdown and operation temperature regulation of the heat pipe cooling reactor, can solve the difficult problem that the heat pipe pile is difficult to control in application scenes such as deep space, deep sea and the like, and can further improve the safety and reliability of the heat pipe pile system.
Under different operation conditions, the invention has three working modes, and the specific steps are as follows:
(1) In the normal operation process of the reactor, when the temperature in the reactor core is increased due to disturbance of external load, the elastic coefficient of the temperature control spring 8 is reduced, the elastic force of the compression spring 1 in the heat pipe exchanger 4 is kept unchanged, the resultant force of the temperature control spring 8 and the compression spring 1 can enable the control rod 5 to move into the heat pipe reactor, negative reactivity is introduced, and the power of the reactor is reduced.
(2) When the heat in the reactor core 11 can not be smoothly led out under the working condition, the temperature in the reactor core is rapidly increased, if the temperature of the control rod 5 limiter 7 in the reactor core exceeds 1500K, the control rod 5 limiter 77 is melted, the temperature control spring 8 can not provide supporting force for the control rod 5, the control rod 5 is rapidly inserted into the reactor core under the action of the compression spring 1, a large amount of negative reactivity is introduced, the shutdown of the reactor is realized, and serious reactor core meltdown accidents are avoided.
(3) During the start-up process, the electric adjusting device 13 is used for adjusting the initial position of the control rod 5, so that the reactor can be in a critical state at different power levels, and the operating temperature of the reactor is controlled.
In the description of the present invention, it should be understood that the terms "longitudinal," "transverse," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," and the like indicate or are based on the orientation or positional relationship shown in the drawings, merely to facilitate description of the present invention, and do not indicate or imply that the devices or elements referred to must have a particular orientation, be constructed and operated in a particular orientation, and thus should not be construed as limiting the present invention.
The above embodiments are only illustrative of the preferred embodiments of the present invention and are not intended to limit the scope of the present invention, and various modifications and improvements made by those skilled in the art to the technical solutions of the present invention should fall within the protection scope defined by the claims of the present invention without departing from the design spirit of the present invention.
Claims (10)
1. A power automation control system for a heat pipe cooled reactor, comprising:
a heat pipe exchanger (4);
the reactor core (11) comprises a reflecting layer and a shielding (10), a core metal matrix (12) is arranged in the reflecting layer and the shielding (10), a plurality of fuel rods (9) are arranged in the core metal matrix (12), the heat pipe heat exchanger (4) is arranged above the reactor core (11), a heat exchange element is arranged between the heat pipe heat exchanger (4) and the reactor core (11), and a central hole is formed in the top surface of the core metal matrix (12);
the control part, the control part includes control rod (5), hold the chamber has been seted up to the bottom surface of heat pipe heat exchanger (4), hold intracavity rigid coupling and have protection casing (6), the bottom of protection casing (6) with reactor core metal base member (12) top surface welding, control rod (5) top sets up in protection casing (6), the bottom of control rod (5) is run through reactor core base metal body and be located in the center hole, the top of control rod (5) is provided with the locating part, the bottom of control rod (5) is provided with the locating part down.
2. A power automation system for a heat pipe cooled reactor according to claim 1, wherein: the upper limiting part comprises a compression spring (1), the top surface of the compression spring (1) is fixedly connected with the top surface of the inner cavity of the protection shell (6), the bottom surface of the compression spring (1) is abutted with the top surface of the control rod (5), and a fixing device (3) is fixedly connected outside the control rod (5);
the fixing device (3) comprises a fixing ring, wherein the outer wall of the fixing ring is fixedly connected with a sliding ring through a connecting rod, and the outer wall of the sliding ring is in sliding contact with the inner wall of the shell.
3. A power automation system for a heat pipe cooled reactor according to claim 2, wherein: the lower limiting piece comprises a temperature control spring (8), an electric adjusting device (13) is fixedly connected to the bottom surface of the inner cavity of the central hole, the output end of the electric adjusting device (13) is fixedly connected with the bottom of the temperature control spring (8), a limiter (7) is sleeved at the bottom of the control rod (5), the top surface of the temperature control spring (8) is abutted to the bottom surface of the limiter (7), and the inner diameter of the temperature control spring (8) is larger than the outer diameter of the control rod (5);
the bottom surface top surface of stopper (7) sets up to groove structure, just groove structure with control stick (5) bottom butt.
4. A power automation system for a heat pipe cooled reactor according to claim 3, wherein: the reactor core metal matrix (12) is of a cylindrical structure, the center hole is formed in the center of the top surface of the reactor core metal matrix (12), the top surface of the reactor core metal matrix (12) is provided with a plurality of heat pipe holes and fuel holes at equal intervals around the circumference of the center hole, and a plurality of fuel rods (9) are respectively positioned in a plurality of the fuel holes.
5. A power automation system for a heat pipe cooled reactor according to claim 4, wherein: the heat exchange element comprises a plurality of high-temperature heat pipes (2), a condensing section of each high-temperature heat pipe (2) is inserted into the heat pipe heat exchanger (4), and an evaporating section of each high-temperature heat pipe (2) penetrates through the reflecting layer and the shielding (10) and is inserted into the holes of the heat pipe.
6. A power automation system for a heat pipe cooled reactor according to claim 5, wherein: the fuel rod (9) is made of uranium dioxide.
7. A power automation system for a heat pipe cooled reactor as claimed in claim 6, wherein: the operating working medium of the high-temperature heat pipe (2) is sodium.
8. A power automation system for a heat pipe cooled reactor as claimed in claim 7, wherein: the material of the core metal matrix (12) is 316 stainless steel.
9. A power automation system for a heat pipe cooled reactor as claimed in claim 8, wherein: the control rod (5) is made of B 4 C, the boron content of the control rod (5) is sequentially increased along the bottom-to-top direction of the control rod (5).
10. A power automation system for a heat pipe cooled reactor as claimed in claim 9, wherein: the melting temperature of the limiter (7) is 1500K.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202310058367.8A CN116130122B (en) | 2023-01-18 | 2023-01-18 | Automatic power control system for heat pipe cooling reactor |
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| CN202310058367.8A CN116130122B (en) | 2023-01-18 | 2023-01-18 | Automatic power control system for heat pipe cooling reactor |
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| CN116130122B CN116130122B (en) | 2023-08-11 |
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