CN112216414B - Nuclear reactor and method for controlling oxygen concentration in nuclear reactor - Google Patents
Nuclear reactor and method for controlling oxygen concentration in nuclear reactor Download PDFInfo
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- CN112216414B CN112216414B CN202010928989.8A CN202010928989A CN112216414B CN 112216414 B CN112216414 B CN 112216414B CN 202010928989 A CN202010928989 A CN 202010928989A CN 112216414 B CN112216414 B CN 112216414B
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- metal coolant
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- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 title claims abstract description 229
- 239000001301 oxygen Substances 0.000 title claims abstract description 229
- 229910052760 oxygen Inorganic materials 0.000 title claims abstract description 229
- 238000000034 method Methods 0.000 title claims abstract description 14
- 239000007789 gas Substances 0.000 claims abstract description 137
- 239000002826 coolant Substances 0.000 claims abstract description 120
- 229910001338 liquidmetal Inorganic materials 0.000 claims abstract description 107
- 230000002093 peripheral effect Effects 0.000 claims abstract description 18
- 230000001105 regulatory effect Effects 0.000 claims abstract description 15
- 239000007788 liquid Substances 0.000 claims description 13
- 239000011261 inert gas Substances 0.000 claims description 7
- 230000001276 controlling effect Effects 0.000 claims description 6
- 238000004891 communication Methods 0.000 claims description 4
- 230000007797 corrosion Effects 0.000 abstract description 4
- 238000005260 corrosion Methods 0.000 abstract description 4
- 239000000463 material Substances 0.000 abstract description 4
- 238000001514 detection method Methods 0.000 description 7
- 229910044991 metal oxide Inorganic materials 0.000 description 6
- 150000004706 metal oxides Chemical class 0.000 description 6
- 238000006243 chemical reaction Methods 0.000 description 5
- 230000000712 assembly Effects 0.000 description 3
- 238000000429 assembly Methods 0.000 description 3
- 230000004308 accommodation Effects 0.000 description 2
- 230000009471 action Effects 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 239000002923 metal particle Substances 0.000 description 2
- 238000001556 precipitation Methods 0.000 description 2
- 230000005856 abnormality Effects 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 229910021645 metal ion Inorganic materials 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 239000002244 precipitate Substances 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
- G21C17/025—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators for monitoring liquid metal coolants
-
- 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
- G21C15/243—Promoting flow of the coolant for liquids
- G21C15/247—Promoting flow of the coolant for liquids for liquid metals
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a nuclear reactor and a control method of oxygen concentration in the nuclear reactor, the nuclear reactor comprises a reactor container, a reactor core, a steam generator, a control rod assembly, an air supply device, an oxygen measuring device and an oxygen regulating device, wherein liquid metal coolant is arranged in the reactor container, the reactor core is arranged in the reactor container, the steam generator is arranged in a peripheral annular cavity of the reactor container, the control rod assembly is arranged in the reactor container and is positioned right above the reactor core, an air outlet of the air supply device is positioned above the reactor core and is spaced from the reactor core in the vertical direction, the air supply device is used for conveying oxygen and circulating control gas into the liquid metal coolant, the oxygen measuring device is used for detecting the oxygen concentration in the liquid metal coolant, and the oxygen regulating device is connected with the air supply device and the oxygen measuring device to regulate the oxygen amount conveyed into the liquid metal coolant by the air supply device. The nuclear reactor of the invention can slow down the corrosion of structural materials and improve the circulating flow speed of the coolant.
Description
Technical Field
The present invention relates to the technical field of nuclear reactors, and in particular to a nuclear reactor using liquid metal as a coolant and a method for controlling oxygen concentration in a nuclear reactor.
Background
A nuclear reactor, also known as an atomic energy reactor or reactor, is a device that can sustain a controlled, self-sustaining, chain-type nuclear fission reaction to achieve nuclear energy utilization. The primary loop in the nuclear reactor is provided with a coolant, and the coolant needs to circularly flow to continuously transfer heat energy released by the fission reaction of the nuclear fuel in the core to the steam generator to generate steam, so that the steam turbine is driven to do work, and the reliable operation of the primary loop system in the nuclear reactor is ensured. Wherein the nuclear reactor is classified into a reactor in which a coolant is forcibly circulated and a reactor in which the coolant is naturally circulated according to a coolant circulation manner.
Disclosure of Invention
The present application has been made on the basis of findings and knowledge of the following facts and technical problems.
The reactor with forced circulation of the coolant in the related art needs to be provided with a complex cooling pipeline in a container, has a relatively complex structure and has a relatively large volume; in the reactor in which the coolant is naturally circulated in the related art, the flow rate of the coolant is relatively low, and the safety and reliability of the operation of the reactor are reduced.
For nuclear reactors using liquid metal (e.g., lead), such as lead-cooled fast reactors, there is a problem in that the coolant is prone to corrosion of components within the reactor in high temperature environments.
The present invention aims to solve at least one of the technical problems in the related art to some extent.
Therefore, the invention provides a nuclear reactor, which can effectively slow down the corrosion of structural materials, reduce the volume of the nuclear reactor and improve the circulating flow speed of coolant.
The invention also provides a control method of the oxygen concentration in the nuclear reactor, which can feed back the information of the oxygen concentration in the liquid metal coolant in real time to realize the accurate control of the oxygen amount.
A nuclear reactor according to an embodiment of the first aspect of the present invention includes: a reactor vessel having a liquid metal coolant therein; a core provided at a middle lower portion within the reactor vessel; the steam generator is arranged in the peripheral annular cavity of the reactor vessel; a control rod assembly disposed within the reactor vessel and directly above the core; the gas supply device comprises a gas outlet which is positioned above the reactor core and is spaced from the reactor core in the up-down direction, and the gas supply device conveys oxygen and circulating control gas into the liquid metal coolant through the gas outlet; an oxygen measuring device for detecting an oxygen concentration within the liquid metal coolant; and the oxygen adjusting device is connected with the air supply device and the oxygen measuring device to adjust the oxygen quantity delivered into the liquid metal coolant by the air supply device according to the oxygen concentration detected by the oxygen measuring device.
According to the nuclear reactor provided by the embodiment of the invention, the oxygen adjusting device, the air supply device and the oxygen measuring device are arranged, and the air supply device and the oxygen measuring device are connected with the oxygen adjusting device, so that the oxygen supply flow of the air supply device can be adjusted by utilizing the oxygen adjusting device according to the detection information of the oxygen measuring device, the oxygen amount introduced into the liquid metal coolant is suitable for increasing the flow speed of the liquid metal coolant, increasing the energy supply efficiency of the nuclear reactor, preventing the structural members in the nuclear reactor from being corroded, avoiding the precipitation of metal oxides, and ensuring the stability and heat exchange capacity of the liquid metal coolant. In addition, the bubbles are suitable for floating independently under the action of density difference, and special flow pipelines and driving equipment are not required to be arranged, so that the purposes of optimizing the space layout in the reactor container and reducing the volume of the nuclear reactor are achieved.
In some embodiments, the liquid level of the liquid metal coolant is a predetermined distance from the interior top surface of the reactor vessel to form a circulation control gas-containing space, and the gas supply device has a circulation control gas inlet in communication with the circulation control gas-containing space.
In some embodiments, the nuclear reactor further includes a barrel disposed within the reactor vessel above the core, and the gas outlet is located within the barrel.
In some embodiments, the barrel and the core are arranged generally coaxially and the cross-sectional area of the barrel is greater than the cross-sectional area of the core, and the air outlet is located outside of and spaced apart from the core in a radial direction of the core.
In some embodiments, a portion of the control rod assembly is located within the barrel, an annular region is formed between the control rod assembly and the inner peripheral wall of the barrel, and the air outlet of the air supply is located within the annular region.
In some embodiments, the steam generator is disposed between an outer peripheral wall of the barrel and an inner peripheral wall of the reactor vessel.
In some embodiments, the air supply device includes an oxygen reservoir for storing oxygen and an air pump connected to the oxygen reservoir, and the oxygen adjustment device is connected to the oxygen reservoir to adjust the amount of oxygen supplied from the oxygen reservoir to the air pump based on the oxygen concentration detected by the oxygen measuring device.
In some embodiments, the air supply device further comprises: a first pipe, a first end of which is connected with the air pump; the second pipe is sleeved outside the first pipe, the first end of the second pipe is connected with the air pump, an annular channel is formed between the first pipe and the second pipe, a circulation control gas inlet is formed in the second pipe, the liquid level of the liquid metal coolant is a preset distance from the inner top surface of the reactor container to form a circulation control gas accommodating space, and the circulation control gas accommodating space is communicated with the circulation control gas inlet so that the circulation control gas enters the annular channel through the circulation control gas inlet; the mixer is connected with the second end of the first pipe and the second end of the second pipe and is used for mixing oxygen in the first pipe and circulating control gas in the annular channel, and the air outlet is formed on the mixer.
In some embodiments, the first tube and the second tube each extend in an up-down direction, the circulation control gas is an inert gas, and the gas outlet is formed at a top of the mixer.
In some embodiments, the oxygen measuring device has a plurality of oxygen measuring points, wherein one oxygen measuring point is located substantially at the liquid level of the liquid metal coolant.
The control method of the oxygen concentration in the nuclear reactor according to the embodiment of the second aspect of the present invention includes the steps of:
supplying oxygen and a circulation control gas into a liquid metal coolant in a nuclear reactor by a gas supply device including a gas outlet located above and spaced apart from the core in an up-down direction; detecting the oxygen concentration in the liquid metal coolant by an oxygen measuring device; and regulating the amount of oxygen which is delivered into the liquid metal coolant by the air supply device through an oxygen regulating device according to the oxygen concentration detected by the oxygen measuring device.
According to the control method for the oxygen concentration in the nuclear reactor, the oxygen concentration in the liquid metal coolant is detected by the oxygen measuring device, and the oxygen amount conveyed into the liquid metal coolant by the gas supply device is regulated according to the oxygen concentration detected by the oxygen measuring device, so that the oxygen concentration information in the liquid metal coolant can be fed back in real time, the accurate control of the oxygen amount is realized, the introduced oxygen amount in the liquid metal coolant is further suitable for increasing the flow speed of the liquid metal coolant, the energy supply efficiency of the nuclear reactor is increased, structural members in the nuclear reactor are protected from being corroded, meanwhile, metal oxides are prevented from being separated out, and the stability and the heat exchange capacity of the liquid metal coolant are ensured.
In some embodiments, the step of supplying oxygen and a cycle control gas into a liquid metal coolant in a nuclear reactor via a gas supply includes: oxygen is supplied from an oxygen reservoir to the liquid metal coolant by an air pump.
In some embodiments, the step of adjusting the amount of oxygen delivered into the liquid metal coolant by the gas supply device via an oxygen adjustment device comprises: the oxygen adjusting means adjusts the amount of oxygen supplied from the oxygen reservoir to the air pump; the oxygen amount in the air pump is delivered into the liquid metal coolant.
In some embodiments, the recycle control gas is an inert gas.
Drawings
FIG. 1 is a schematic view of a nuclear reactor according to an embodiment of the invention.
Fig. 2 is a schematic view of a gas supply device of a nuclear reactor according to an embodiment of the present invention.
Reference numerals:
a nuclear reactor 1;
a reactor vessel 10;
a core 20;
a steam generator 30;
a control rod assembly 40;
a gas supply device 50; an air outlet 501; a circulation control gas inlet 502; a storage 503; an air pump 504; a first tube 505; a second tube 506; a mixer 507;
an oxygen measuring device 60;
an oxygen regulating device 70;
a barrel 80.
Detailed Description
Reference will now be made in detail to embodiments of the present invention, examples of which are illustrated in the accompanying drawings. The embodiments described below by referring to the drawings are illustrative and intended to explain the present invention and should not be construed as limiting the invention. In the description of the present invention, it should be understood that the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential", etc. indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings are merely for convenience in describing the present invention and simplifying the description, and do not indicate or imply that the device or element being referred to must have a specific orientation, be configured and operated in a specific orientation, and therefore should not be construed as limiting the present invention.
As shown in fig. 1 and 2, a nuclear reactor 1 according to an embodiment of the present invention includes a reactor vessel 10, a core 20, a steam generator 30, a control rod assembly 40, an air supply device 50, an oxygen measuring device 60, an oxygen regulating device 70, and a barrel 80.
The reactor vessel 10 has a liquid metal coolant therein, and the core 20 is provided at a middle lower portion in the reactor vessel 10. It will be appreciated that the liquid metal coolant is used to cool the core 20, the metal coolant flowing within the reactor vessel 10 and carrying the thermal energy generated by the core 20 out of the nuclear reactor 1, effecting the thermal energy output of the nuclear reactor 1.
The steam generator 30 is disposed within the peripheral annulus of the reactor vessel 10. The steam generator 30 may exchange heat with a metal coolant to form high temperature steam within the steam generator 30, which may enter a steam turbine to perform work, thereby converting thermal energy generated by the nuclear reactor 1 into electrical or mechanical energy.
The control rod assemblies 40 are disposed in the reactor vessel 10 and directly above the core 20, the control rod assemblies 40 can be used to compensate fuel consumption and adjust reaction rates, and the control rod assemblies 40 can rapidly stop a chain reaction when an abnormality occurs in the nuclear reactor 1, thereby avoiding an accident occurring in the nuclear reactor 1.
The air supply device 50 includes an air outlet 501, and the air outlet 501 is located above the core 20 and spaced apart from the core 20 in the up-down direction, so that interference between the air outlet 501 and the core 20 can be avoided, and smoothness of air outlet 501 is ensured.
The gas supply means 50 delivers oxygen and a circulation control gas into the liquid metal coolant through a gas outlet 501. As shown in fig. 1, the reactor core 20 is disposed at a middle lower portion in the reactor vessel 10, the gas outlet 501 is located at a position adjacent to an upper end of the reactor core 20, and oxygen and circulation control gas discharged through the gas outlet 501 enter the liquid metal coolant to form bubbles, the bubbles are adapted to float along a flow path of the liquid metal coolant, and as the bubbles are closer to a liquid surface of the liquid metal coolant, pressure of the bubbles is continuously reduced, and volume of the bubbles is continuously increased, so that an overall flow of the coolant system is driven, and a heating efficiency of the nuclear reactor 1 is further enhanced.
In addition, the liquid metal coolant has stronger corrosiveness in a high-temperature environment, and oxygen is introduced into the liquid metal coolant, so that the surface of a structural member in direct contact with the liquid metal coolant in the nuclear reactor 1 can be oxidized, the liquid metal coolant is separated from the structural member by an oxide film formed on the surface of the structural member, the corrosion in the structural member is avoided, and the service life and safety of the nuclear reactor 1 are improved.
The oxygen measuring device 60 is used for detecting the oxygen concentration in the liquid metal coolant, and the oxygen adjusting device 70 is connected with the air supply device 50 and the oxygen measuring device 60 to adjust the oxygen amount delivered into the liquid metal coolant by the air supply device 50 according to the oxygen concentration detected by the oxygen measuring device 60. In other words, the information of the oxygen concentration detected by the oxygen measuring device 60 is fed back to the oxygen adjusting device 70, and the oxygen adjusting device 70 instructs the air supplying device 50 to control the air supplying device 50 to adjust the oxygen flow rate based on the information.
It should be noted that, because metal ions exist in the liquid metal coolant, when the oxygen concentration in the liquid metal coolant is too high, the solid metal oxide may precipitate out of the liquid metal coolant, which causes pollution of the liquid metal coolant, and when the oxygen concentration in the liquid metal coolant is too low, the metal oxide film may be thermodynamically dissolved, so that the structural member cannot be protected.
According to the nuclear reactor provided by the embodiment of the invention, the oxygen adjusting device, the air supply device and the oxygen measuring device are arranged, and the air supply device and the oxygen measuring device are connected with the oxygen adjusting device, so that the oxygen supply flow of the air supply device can be adjusted by utilizing the oxygen adjusting device according to the detection information of the oxygen measuring device, the oxygen amount introduced into the liquid metal coolant is suitable for increasing the flow speed of the liquid metal coolant, increasing the energy supply efficiency of the nuclear reactor, preventing the structural members in the nuclear reactor from being corroded, avoiding the precipitation of metal oxides, and ensuring the stability and heat exchange capacity of the liquid metal coolant. In addition, the bubbles are suitable for floating independently under the action of density difference, and special flow pipelines and driving equipment are not required to be arranged, so that the purposes of optimizing the space layout in the reactor container and reducing the volume of the nuclear reactor are achieved.
In some embodiments, as shown in fig. 1, the liquid level of the liquid metal coolant is a predetermined distance from the inner top surface of the reactor vessel 10 to form a circulation control gas-accommodating space, and the gas supply device 50 has a circulation control gas inlet 502 communicating with the circulation control gas-accommodating space. In other words, the circulation control gas accommodation space may serve as a transit space for the circulation control gas, and the circulation control gas accommodation space is adapted to accommodate the circulation control gas that floats from the liquid surface of the liquid metal coolant, and is also adapted to supply the circulation control gas to the gas supply device 50.
Specifically, as shown in fig. 1, the control circulating gas may be inert gas, after the gas supply device 50 delivers the control circulating gas into the liquid metal coolant, the control circulating gas floats up to the liquid level of the liquid metal coolant under the effect of the density difference, and the inert control circulating gas is not dissolved in the liquid metal coolant and is not chemically reacted with the metal particles, so that finally the control circulating gas which completes one flow cycle is separated from the liquid metal coolant and stored in the circulation control gas accommodating space.
The circulation control gas inlet 502 is communicated with the circulation control gas accommodating space so as to extract the circulation control gas from the circulation control gas accommodating space in the next flowing circulation, thereby realizing the circulation of the circulation control gas.
In some embodiments, as shown in fig. 1, the nuclear reactor 1 further includes a barrel 80, the barrel 80 being disposed within the reactor vessel 10 above the core 20, and the gas outlet 501 being located within the barrel 80. Therefore, the cylindrical part can define a relatively independent accommodating space, and the air outlet in the cylindrical part is suitable for being spaced from other structural parts (such as a reactor core) in the nuclear reactor, so that mutual interference is avoided, and the operation reliability of the nuclear reactor 1 is improved.
In some embodiments, as shown in FIG. 1, the barrel 80 and the core 20 are disposed generally coaxially and the cross-sectional area of the barrel 80 is greater than the cross-sectional area of the core 20, with the air outlet 501 being located outside of the core 20 in the radial direction of the core 20 and spaced apart from the core 20 in the radial direction of the core 20. Therefore, by arranging the cylindrical member with a larger cross section, the internal accommodating space of the cylindrical member can be increased, and the arrangement of the air outlet is facilitated.
In some embodiments, as shown in FIG. 1, a portion of the control rod assembly 40 is positioned within the barrel 80, with an annular region formed between the control rod assembly 40 and the inner peripheral wall of the barrel 80, and the air outlet 501 of the air supply 50 is positioned within the annular region. Therefore, the cylindrical part can be used for separating the control rod group from other parts in the nuclear reactor, so that the other parts are prevented from interfering with the control rod group, and the reliability of the disconnection chain reaction of the control rod group is improved.
In addition, as shown in fig. 1, a part of the air supply device 50 is located in the annular area, and the plurality of air supply devices 50 may be distributed at intervals along the circumferential direction of the annular area, it is understood that the mixed gas output by the air outlet 501 located in the annular area is suitable for floating in the annular area, so that a floating obstacle can be avoided, the gas floating speed can be increased, and the flow rate of the liquid metal coolant can be increased.
In some embodiments, as shown in fig. 1, the steam generator 30 is disposed between the outer peripheral wall of the cartridge 80 and the inner peripheral wall of the reactor vessel 10. Therefore, the steam generator, the control rod assembly and the air outlet can be separated, mutual interference among elements is avoided, meanwhile, the internal layout of the nuclear reactor is optimized, the contact area of the steam generator and the liquid metal coolant is increased, and the heat exchange efficiency is further improved.
In some embodiments, as shown in fig. 2, the air supply device 50 includes an oxygen reservoir 503 for storing oxygen and an air pump 504 connected to the oxygen reservoir 503, and the oxygen adjusting device 70 is connected to the oxygen reservoir 503 to adjust the amount of oxygen supplied from the oxygen reservoir to the air pump 504 according to the oxygen concentration detected by the oxygen measuring device 60.
Specifically, when the oxygen concentration in the liquid metal coolant detected by the oxygen measuring device 60 is low, the oxygen adjusting device 70 is adapted to adjust the output flow rate of the oxygen reservoir 503 according to the detection information of the oxygen measuring device 60, and the air pump 504 is adapted to drive oxygen to the air outlet 501.
When the oxygen concentration in the liquid metal coolant detected by the oxygen measuring device 60 is high, the oxygen adjusting device 70 is adapted to adjust the output flow rate of the oxygen reservoir 503 according to the detection information of the oxygen measuring device 60. Therefore, the oxygen concentration in the liquid metal coolant can be intelligently adjusted by utilizing the oxygen measuring device, the oxygen adjusting device and the air supply device, and the stability and the heat exchange capacity of the liquid metal coolant are ensured.
In some embodiments, as shown in fig. 1 and 2, the gas supply device 50 further includes a first pipe 505 and a second pipe 506, a first end of the first pipe 505 (an upper end of the first pipe 505 in fig. 2) is connected to the gas pump 504, the second pipe 506 is sleeved outside the first pipe 505, a first end of the second pipe 506 (an upper end of the second pipe 506 in fig. 2) is connected to the gas pump 504, an annular passage is formed between the first pipe 505 and the second pipe 506, a circulation control gas inlet 502 is provided on the second pipe 506, and a liquid level of the liquid metal coolant is a predetermined distance from an inner top surface of the reactor vessel 10 to form a circulation control gas accommodating space, and the circulation control gas accommodating space communicates with the circulation control gas inlet 502 so that the circulation control gas enters the annular passage through the circulation control gas inlet 502.
As shown in fig. 2, the first tube 505 extends in the up-down direction, the upper end of the first tube 505 is connected to the air pump 504, the second tube 506 is sleeved outside the first tube 505 and the second tube 506 extends in the same direction as the first tube 505, and the upper end of the second tube 506 is connected to the air pump 504.
An annular passage extending in the up-down direction is formed between the outer peripheral wall of the first tube 505 and the inner peripheral wall of the second tube 506, and a circulation control gas inlet 502 is provided on the second tube 506 adjacent to the upper end of the second tube 506, and the circulation gas in the circulation control gas accommodating space is adapted to flow into the annular passage through the circulation control gas inlet 502. Therefore, the pipeline layout of the gas supply device can be optimized, the space ratio of the pipeline in the reactor vessel is reduced, and the co-current flow of oxygen and circulating control gas is realized.
The mixer 507 is connected to a second end of the first pipe 505 (a lower end of the first pipe 505 in fig. 2) and a second end of the second pipe 506 (a lower end of the second pipe 506 in fig. 2) for mixing oxygen in the first pipe 505 and a circulation control gas in the annular passage, and an air outlet 501 is formed on the mixer 507, preferably the air outlet 501 is formed at a top of the mixer 507.
As shown in fig. 2, the mixer 507 is connected to the lower end of the first pipe 505 and the lower end of the second pipe 506, and the circulation control gas is mixed with oxygen in the mixer 507, so that the proportion of the circulation control gas can be reduced when the oxygen content needs to be increased, and the proportion of the circulation control gas can be increased when the oxygen content needs to be reduced.
In some embodiments, the oxygen measuring device 60 has a plurality of oxygen measuring points, wherein one oxygen measuring point is located substantially at the liquid level of the liquid metal coolant, and the other oxygen measuring points are located below the liquid level of the liquid metal coolant. Therefore, the accuracy of the detection data of the oxygen measuring device can be improved, and the accurate control of the oxygen content in the liquid metal coolant is facilitated.
A nuclear reactor 1 according to some specific examples of the invention is described below with reference to fig. 1-2.
As shown in fig. 1-2, a nuclear reactor 1 includes a reactor vessel 10, a core 20, a steam generator 30, a control rod assembly 40, a gas supply 50, an oxygen measuring device 60, and an oxygen regulating device 70.
The reactor core 20, the steam generator 30, the control rod assembly 40, the gas supply device 50, the oxygen measuring device 60, the oxygen adjusting device 70 and the cylindrical member 80 are arranged in a peripheral annular cavity of the reactor vessel 10, a liquid metal coolant is arranged in the reactor vessel 10, and a circulation control gas accommodating space is formed between the liquid level of the liquid metal coolant and the top of the reactor vessel 10.
The reactor vessel 10 has a core 20 support provided on an inner bottom wall thereof, the core 20 is placed on the core 20 support, the cylindrical member 80 is provided directly above the core 20, an annular space is provided between an outer peripheral surface of the cylindrical member 80 and an inner peripheral surface of the reactor vessel 10, and the steam generator 30 is provided in the annular space and also provided on an outer periphery of the cylindrical member 80.
The control rod assembly 40 is provided in the cylindrical member 80 with a space between the outer bottom wall of the control rod assembly 40 and the inner bottom wall of the cylindrical member 80, and an annular space is formed between the outer circumferential wall of the control rod assembly 40 and the inner circumferential wall of the cylindrical member 80, and the air supply device 50 is provided to penetrate in the vertical direction in the space.
The air supply device 50 comprises an oxygen reservoir 503, an air pump 504, a first pipe 505, a second pipe 506, a mixer 507 and an air outlet 501, wherein the air pump 504 is arranged above the mixer 507 at intervals, the first pipe 505 and the second pipe 506 are connected between the air pump 504 and the mixer 507, the first pipe 505 and the second pipe 506 extend along the vertical direction, the second pipe 506 is sleeved on the first pipe 505, and an annular channel extending up and down is formed between the first pipe 505 and the second pipe 506.
The upper ends of the first pipe 505 and the second pipe 506 are connected to the air pump 504, the lower ends of the first pipe 505 and the second pipe 506 are connected to the mixer 507, the air outlet 501 is provided at the top of the mixer 507, the air outlet 501 is provided in the barrel 80 and spaced apart from the core 20 in the up-down direction, the second pipe 506 is provided with the circulation control gas inlet 502 adjacent to the upper end of the second pipe 506, and the circulation control gas inlet 502 communicates with the circulation control gas accommodating space.
The oxygen measuring device 60 is connected with the oxygen adjusting device 70, the oxygen adjusting device 70 is connected with the oxygen storage 503, the oxygen storage 503 is connected with the air pump 504, the air pump 504 is suitable for driving oxygen in the oxygen storage 503 into the outlet mixer 507, circulation control gas in the circulation control gas accommodating space flows into the annular channel through the circulation control gas inlet 502, the air pump 504 is suitable for driving the circulation control gas into the outlet mixer 507, and the oxygen is discharged into the liquid metal coolant through the air outlet 501 after being mixed with the circulation control gas.
Specifically, when the oxygen concentration in the liquid metal coolant detected by the oxygen measuring device 60 is low, the oxygen adjusting device 70 is adapted to adjust the oxygen output flow rate of the oxygen reservoir 503 according to the detection information of the oxygen measuring device 60, and when the oxygen concentration in the liquid metal coolant detected by the oxygen measuring device 60 is high, the oxygen adjusting device 70 is adapted to adjust the oxygen output flow rate of the oxygen reservoir 503 according to the detection information of the oxygen measuring device 60.
The control method of the oxygen concentration in the nuclear reactor according to the embodiment of the invention comprises the following steps:
oxygen and a circulation control gas are supplied into a liquid metal coolant in a nuclear reactor by a gas supply device including a gas outlet located above and spaced apart from the core in an up-down direction. The oxygen concentration in the liquid metal coolant is detected by the oxygen measuring device, and the oxygen amount delivered into the liquid metal coolant by the air supply device is regulated by the oxygen regulating device according to the oxygen concentration detected by the oxygen measuring device.
Specifically, the oxygen and the circulation control gas form a mixed gas in the gas supply device, the mixed gas is suitable for being discharged into the liquid metal coolant through the gas outlet, then floats up to the liquid level of the liquid metal coolant and is separated from the liquid metal coolant, and in the process, the mixed gas floats up to drive the liquid metal coolant to flow.
According to the control method for the oxygen concentration in the nuclear reactor, the oxygen concentration in the liquid metal coolant is detected by the oxygen measuring device, and the oxygen amount conveyed into the liquid metal coolant by the gas supply device is regulated according to the oxygen concentration detected by the oxygen measuring device, so that the oxygen concentration information in the liquid metal coolant can be fed back in real time, the accurate control of the oxygen amount is realized, the introduced oxygen amount in the liquid metal coolant is further suitable for increasing the flow speed of the liquid metal coolant, the energy supply efficiency of the nuclear reactor is increased, structural members in the nuclear reactor are protected from being corroded, meanwhile, metal oxides are prevented from being separated out, and the stability and the heat exchange capacity of the liquid metal coolant are ensured.
Further, the step of supplying oxygen and a circulation control gas into a liquid metal coolant in a nuclear reactor by a gas supply device comprises: oxygen is supplied from an oxygen reservoir to the liquid metal coolant by an air pump.
Further, the step of adjusting the amount of oxygen supplied into the liquid metal coolant by the gas supply means by the oxygen adjusting means includes: the oxygen regulating device regulates the amount of oxygen supplied from the oxygen reservoir to the air pump and delivers the amount of oxygen in the air pump into the liquid metal coolant.
Specifically, the air pump drives oxygen to flow into the liquid metal coolant from the oxygen storage, and after the oxygen content in the liquid metal coolant is detected by the oxygen measuring device, the oxygen quantity supplied to the air pump from the oxygen storage is controlled by the oxygen regulating device, so that a control cycle is formed, and the accurate control of the oxygen content in the liquid metal coolant is realized.
In some embodiments, the circulation control gas is an inert gas, and it is understood that the inert control circulation gas does not dissolve in the liquid metal coolant and does not chemically react with the metal particles, and thus, the circulation control gas can be recycled by using the inert gas as the circulation control gas.
In the description of the present specification, a description referring to terms "one embodiment," "some embodiments," "examples," "specific examples," or "some examples," etc., means that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present invention. In this specification, schematic representations of the above terms are not necessarily directed to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, the different embodiments or examples described in this specification and the features of the different embodiments or examples may be combined and combined by those skilled in the art without contradiction.
Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include at least one such feature. In the description of the present invention, the meaning of "plurality" means at least two, for example, two, three, etc., unless specifically defined otherwise.
In the present invention, unless explicitly specified and limited otherwise, the terms "mounted," "connected," "secured," and the like are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally formed; may be mechanically connected, may be electrically connected or may be in communication with each other; either directly or indirectly, through intermediaries, or both, may be in communication with each other or in interaction with each other, unless expressly defined otherwise. The specific meaning of the above terms in the present invention can be understood by those of ordinary skill in the art according to the specific circumstances.
In the present invention, unless expressly stated or limited otherwise, a first feature "up" or "down" a second feature may be the first and second features in direct contact, or the first and second features in indirect contact via an intervening medium. Moreover, a first feature being "above," "over" and "on" a second feature may be a first feature being directly above or obliquely above the second feature, or simply indicating that the first feature is level higher than the second feature. The first feature being "under", "below" and "beneath" the second feature may be the first feature being directly under or obliquely below the second feature, or simply indicating that the first feature is less level than the second feature.
While embodiments of the present invention have been shown and described above, it will be understood that the above embodiments are illustrative and not to be construed as limiting the invention, and that variations, modifications, alternatives and variations may be made to the above embodiments by one of ordinary skill in the art within the scope of the invention.
Claims (12)
1. A nuclear reactor, comprising:
a reactor vessel having a liquid metal coolant therein;
a core provided at a middle lower portion within the reactor vessel;
the steam generator is arranged in the peripheral annular cavity of the reactor vessel;
a control rod assembly disposed within the reactor vessel and directly above the core;
the air supply device comprises an oxygen reservoir for storing oxygen and an air pump connected with the oxygen reservoir;
the gas supply device further comprises a gas outlet which is positioned above the reactor core and is spaced from the reactor core in the up-down direction, and the gas supply device directly conveys oxygen and circulating control gas into the liquid metal coolant through the gas outlet;
the air supply device further includes:
a first pipe, a first end of which is connected with the air pump;
the second pipe is sleeved outside the first pipe, the first end of the second pipe is connected with the air pump, an annular channel is formed between the first pipe and the second pipe, a circulating control gas inlet is formed in the position, adjacent to the upper end of the second pipe, the liquid level of the liquid metal coolant is a preset distance from the inner top surface of the reactor container to form a circulating control gas accommodating space, and the circulating control gas accommodating space is communicated with the circulating control gas inlet so that circulating control gas enters the annular channel through the circulating control gas inlet;
a mixer connected to the second end of the first tube and the second end of the second tube for mixing the oxygen in the first tube and the circulation control gas in the annular channel, the gas outlet being formed on the mixer;
an oxygen measuring device for detecting an oxygen concentration within the liquid metal coolant;
and the oxygen adjusting device is connected with the air supply device and the oxygen measuring device to adjust the oxygen quantity delivered into the liquid metal coolant by the air supply device according to the oxygen concentration detected by the oxygen measuring device in real time.
2. The nuclear reactor of claim 1 wherein the liquid metal coolant level is a predetermined distance from the top interior surface of the reactor vessel to form a circulation control gas receiving space, the gas supply having a circulation control gas inlet in communication with the circulation control gas receiving space.
3. The nuclear reactor of claim 1 or 2, further comprising a barrel member disposed within the reactor vessel above the core, the gas outlet being located within the barrel member.
4. The nuclear reactor of claim 3 wherein the barrel and the core are arranged generally coaxially and the cross-sectional area of the barrel is greater than the cross-sectional area of the core, the gas outlet being located outside of and spaced apart from the core in a radial direction of the core.
5. A nuclear reactor according to claim 3, wherein a portion of the control rod assembly is located within the barrel, an annular region is formed between the control rod assembly and an inner peripheral wall surface of the barrel, and the gas outlet of the gas supply is located within the annular region.
6. A nuclear reactor according to claim 3, wherein the steam generator is provided between an outer peripheral wall surface of the tubular member and an inner peripheral wall surface of the reactor vessel.
7. The nuclear reactor of claim 1, wherein the first tube and the second tube each extend in an up-down direction, the circulation control gas is an inert gas, and the gas outlet is formed at a top of the mixer.
8. The nuclear reactor of any one of claims 1-2, 4-7 wherein the oxygen measuring device has a plurality of oxygen measuring points, one of the oxygen measuring points being located substantially at the level of the liquid metal coolant and the remaining oxygen measuring points being located below the level of the liquid metal coolant.
9. A method for controlling the oxygen concentration in a nuclear reactor as claimed in any one of claims 1 to 8, comprising the steps of:
supplying oxygen and a circulation control gas directly into a liquid metal coolant in a nuclear reactor by a gas supply device including a gas outlet located above and spaced apart from the core in an up-down direction;
detecting the oxygen concentration in the liquid metal coolant in real time through an oxygen measuring device;
and regulating the amount of oxygen which is delivered into the liquid metal coolant by the air supply device through an oxygen regulating device according to the oxygen concentration detected by the oxygen measuring device.
10. The method of controlling oxygen concentration in a nuclear reactor according to claim 9, wherein the step of supplying oxygen and a circulation control gas into a liquid metal coolant in the nuclear reactor through a gas supply device comprises:
oxygen is supplied from an oxygen reservoir to the liquid metal coolant by an air pump.
11. The method of controlling oxygen concentration in a nuclear reactor of claim 10, wherein the step of adjusting the amount of oxygen delivered into the liquid metal coolant by the gas supply device via an oxygen adjustment device comprises:
the oxygen adjusting means adjusts the amount of oxygen supplied from the oxygen reservoir to the air pump;
the oxygen amount in the air pump is delivered into the liquid metal coolant.
12. The method of controlling oxygen concentration in a nuclear reactor according to any one of claims 9 to 11, wherein the circulating control gas is an inert gas.
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Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2003130988A (en) * | 2001-10-23 | 2003-05-08 | Mitsubishi Heavy Ind Ltd | Oxygen concentration monitoring device |
| CN106463187A (en) * | 2014-06-11 | 2017-02-22 | 阿克梅工程公司 | Method and device for regulating concentration of oxygen in reactor facility, and nuclear reactor facility |
| CN107408415A (en) * | 2014-11-11 | 2017-11-28 | 阿克米-工程股份公司 | For the method to refrigerant injection gas and control system and nuclear reactor facility |
| RU181304U1 (en) * | 2017-07-19 | 2018-07-10 | федеральное государственное бюджетное образовательное учреждение высшего образования "Нижегородский государственный технический университет им. Р.Е. Алексеева" (НГТУ) | Nuclear power plant |
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Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2003130988A (en) * | 2001-10-23 | 2003-05-08 | Mitsubishi Heavy Ind Ltd | Oxygen concentration monitoring device |
| CN106463187A (en) * | 2014-06-11 | 2017-02-22 | 阿克梅工程公司 | Method and device for regulating concentration of oxygen in reactor facility, and nuclear reactor facility |
| CN107408415A (en) * | 2014-11-11 | 2017-11-28 | 阿克米-工程股份公司 | For the method to refrigerant injection gas and control system and nuclear reactor facility |
| RU181304U1 (en) * | 2017-07-19 | 2018-07-10 | федеральное государственное бюджетное образовательное учреждение высшего образования "Нижегородский государственный технический университет им. Р.Е. Алексеева" (НГТУ) | Nuclear power plant |
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