CN113345606A - Reactor shutdown control rod and reactor shutdown and cooling integrated system with same - Google Patents
Reactor shutdown control rod and reactor shutdown and cooling integrated system with same Download PDFInfo
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- CN113345606A CN113345606A CN202110466343.7A CN202110466343A CN113345606A CN 113345606 A CN113345606 A CN 113345606A CN 202110466343 A CN202110466343 A CN 202110466343A CN 113345606 A CN113345606 A CN 113345606A
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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
- G21C7/24—Selection of substances for use as neutron-absorbing material
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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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention relates to a shutdown control rod and a reactor shutdown and cooling integrated system with the same. Wherein the outer surface of the shutdown control rod is coated with a neutron absorbing coating; a closed cavity is arranged in the shutdown control rod, and a liquid metal coolant is arranged in the closed cavity; when a shutdown control rod is inserted into the reactor core of the reactor pressure vessel, the neutron absorption coating can absorb neutrons to stop the chain fission reaction of the reactor core, and the liquid metal coolant can absorb heat generated by the chain fission reaction of the reactor core and vaporize the heat, so that the temperature of the reactor core is quickly reduced, and the phenomenon that the temperature of the reactor core is continuously increased due to waste heat and is dangerous is effectively avoided. Because this shutdown control rod can realize the cooling function of reactor core when realizing the shutdown function, realize the emission of waste heat in the reactor core through this passive system, unusual simple and convenient and the security performance is higher.
Description
Technical Field
The invention relates to the technical field of lead-based reactor shutdown, in particular to a shutdown control rod and a reactor shutdown and cooling integrated system with the same.
Background
A lead-based reactor refers to a reactor that utilizes lead or a lead alloy as a coolant. Compared with the traditional reactor, the lead-based reactor has good neutronics, thermal hydraulics and safety characteristics, and is one of the main candidate reactor types of the fourth-generation advanced nuclear energy system at present. In the prior art, a shutdown control rod of a heavy metal cooling reactor such as a lead-based reactor is designed into a plurality of long and thin cylinders, the long and thin cylinders are connected with a control rod driving mechanism in the reactor through a driving rod, and when a shutdown signal sent by a reactor protection system is received by the system, the shutdown control rod can accurately fall into the reactor core through the control rod driving mechanism, so that the shutdown function is realized. Because chain fission reaction takes place in the reactor core, consequently after the shutdown operation, need absorb the waste heat that the chain fission reaction produced in the reactor core and discharge, however the emergent waste heat discharge system that present nuclear power station adopted often is independent of shutdown control rod drive system, still needs extra electric actuator to open the valve and realizes the emission of waste heat in the reactor core, this just makes when meetting emergency, if the valve of opening emergent waste heat discharge system that can not be timely, the reactor core can be because the waste heat and the temperature lasts the rising, and then comparatively dangerous situation appears.
Disclosure of Invention
Based on this, it is necessary to provide a shutdown control rod for the technical problem that the temperature of the reactor core is continuously increased due to the waste heat if the valve of the emergency waste heat removal system cannot be opened in time after shutdown operation because the emergency waste heat removal system of the lead-based reactor and the shutdown control rod driving system are mutually independent, and then dangerous conditions occur.
A shutdown control rod having an outer surface coated with a neutron absorbing coating; a closed cavity is formed in the shutdown control rod, and a liquid metal coolant is arranged in the closed cavity; when the shutdown control rod is inserted into the reactor core of the reactor pressure vessel, the neutron absorption coating can absorb neutrons to stop the chain fission reaction of the reactor core, and the liquid metal coolant can absorb heat generated by the chain fission reaction of the reactor core to be vaporized.
In one embodiment, the shutdown control rod comprises at least:
the neutron absorption coating is coated on the outer surface of the evaporation section, and the liquid metal coolant is positioned in the evaporation section; and
the condensation section (113) is connected with the evaporation section (111), the condensation section is arranged above the evaporation section, and the condensation section is inserted into a cooling water tank; the gas formed by the vaporization of the liquid metal coolant in the evaporation section can rise to the condensation section, and the gas can be cooled by the cooling water tank in the condensation section, so that the liquid metal coolant is liquefied.
In one embodiment, the shutdown control rod further comprises a wick; the liquid absorption core is arranged on the inner wall of the closed cavity and used for absorbing the liquefied metal coolant, and the liquefied metal coolant can flow downwards through the liquid absorption core.
In one embodiment, the shutdown control rod further comprises a counterweight section connected to and located above the condenser section.
The invention also provides a reactor shutdown and cooling integrated system which can solve at least one technical problem.
An integrated reactor shutdown and cooling system, comprising:
a reactor pressure vessel having a reactor core disposed therein;
a cooling water tank located above the core; and
the shutdown control rod has an evaporation section capable of being inserted into the core, and a condensation section capable of extending into the cooling water tank.
In one embodiment, the integrated reactor shutdown and cooling system further comprises a control rod guide sleeve extending through the cooling water tank and positioned above the core, the shutdown control rods being inserted into the control rod guide sleeve.
In one embodiment, the cooling water tank further comprises a cooling jacket pipe sleeved outside the control rod guide sleeve.
In one embodiment, the integrated reactor shutdown and cooling system further comprises a control rod drive mechanism coupled to the shutdown control rod for driving the shutdown control rod to move along the length of the control rod guide sleeve.
In one embodiment, the integrated reactor shutdown and cooling system further comprises a steam pipeline, and one end of the steam pipeline is connected and communicated with the cooling water tank.
In one embodiment, the integrated reactor shutdown and cooling system further comprises:
a chimney;
the passive condenser is connected with the other end of the steam pipeline and is arranged on the chimney; and
and the cooling water pipeline is connected between the passive condenser and the cooling water tank.
The invention has the beneficial effects that:
when the system receives a shutdown signal sent by a reactor protection system, one end of the shutdown control rod, coated with a neutron absorption coating, enters the reactor core of the reactor pressure vessel through a control rod driving mechanism, and the neutron absorption coating absorbs neutrons to stop the chain fission reaction of the reactor core, so that the shutdown function is realized. Because the closed cavity is formed in the shutdown control rod, and the liquid metal coolant is arranged in the closed cavity, the heat generated by the core chain fission reaction is absorbed by the liquid metal coolant, so that the temperature of the core can be quickly reduced, and the dangerous condition caused by continuous rise of the temperature of the core due to waste heat is effectively avoided. Because this shutdown control rod can realize the cooling function of reactor core when realizing the shutdown function, realize the emission of waste heat in the reactor core through this passive system, unusual simple and convenient and the security performance is higher.
The reactor shutdown and cooling integrated system provided by the invention can achieve at least one technical effect.
Drawings
FIG. 1 is a schematic diagram of an integrated reactor shutdown and cooling system provided in accordance with an embodiment of the present invention;
FIG. 2 is an enlarged view of a portion of the integrated reactor shutdown and cooling system shown in FIG. 1 at A;
FIG. 3 is a schematic view of a shutdown control rod of the integrated reactor shutdown and cooling system shown in FIG. 1;
FIG. 4 is a cross-sectional view at B-B of the integrated reactor shutdown and cooling system shown in FIG. 2.
Reference numerals: 100-shutdown control rods; 110-a closed cavity; 111-an evaporation section; 1111-a neutron absorbing coating; 112-middle section; 113-a condensation section; 120-a wick; 130-a counterweight segment; 140-a rod shell; 200-a reactor pressure vessel; 210-a core; 220-a cooling water tank; 221-a cooling jacket; 230-control rod guide sleeve; 240-control rod drive mechanism; 241-a transmission chain; 250-a steam pipeline; 260-passive condenser; 270-chimney; 280-a steam isolation valve; 290-cooling water isolation valve; 300-cooling water pipeline.
Detailed Description
In order to make the aforementioned objects, features and advantages of the present invention comprehensible, embodiments accompanied with figures are described in detail below. In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention. This invention may, however, be embodied in many different forms and should not be construed as limited to the embodiments set forth herein.
In the description of the present invention, it is to be understood that the terms "central," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," "circumferential," and the like are used in the orientations and positional relationships indicated in the drawings for convenience in describing the invention and to simplify the description, and are not intended to indicate or imply that the referenced device or element must have a particular orientation, be constructed and operated in a particular orientation, and are not to be considered limiting of the invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present invention, "a plurality" means at least two, e.g., two, three, etc., unless specifically limited otherwise.
In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," "secured," and the like are to be construed broadly and can, for example, be fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; they may be directly connected or indirectly connected through intervening media, or they may be connected internally or in any other suitable relationship, unless expressly stated otherwise. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
In the present invention, unless otherwise expressly stated or limited, the first feature "on" or "under" the second feature may be directly contacting the first and second features or indirectly contacting the first and second features through an intermediate. Also, a first feature "on," "over," and "above" a second feature may be directly or diagonally above the second feature, or may simply indicate that the first feature is at a higher level than the second feature. A first feature being "under," "below," and "beneath" a second feature may be directly under or obliquely under the first feature, or may simply mean that the first feature is at a lesser elevation than the second feature.
It will be understood that when an element is referred to as being "secured to" or "disposed on" another element, it can be directly on the other element or intervening elements may also be present. When an element is referred to as being "connected" to another element, it can be directly connected to the other element or intervening elements may also be present. The terms "vertical," "horizontal," "upper," "lower," "left," "right," and the like as used herein are for illustrative purposes only and do not denote a unique embodiment.
Referring to FIG. 3, FIG. 3 is a schematic view of a shutdown control rod according to an embodiment of the present invention, which has an outer surface coated with a neutron absorbing coating 1111; a closed cavity 110 is arranged in the shutdown control rod, and a liquid metal coolant is arranged in the closed cavity 110; when the shutdown control rod is inserted into the core 210 of the reactor pressure vessel 200, the neutron absorption coating 1111 can absorb neutrons so that the chain fission reaction of the core 210 is terminated, and the liquid metal coolant can absorb heat generated by the chain fission reaction of the core 210 to be vaporized.
In practical use, when the system receives a shutdown signal sent by the reactor protection system, the shutdown control rod is moved downwards by the control rod drive mechanism 240, so that one end of the shutdown control rod, which is coated with the neutron absorption coating 1111, is inserted downwards into the core 210 of the reactor pressure vessel 200, and then the neutron absorption coating 1111 on the surface of the shutdown control rod can absorb neutrons, so that the chain fission reaction of the core 210 is stopped, and the shutdown function is realized. A closed cavity 110 is arranged in the shutdown control rod, and liquid metal coolant is arranged in the closed cavity 110. When the end of the shutdown control rod coated with the neutron absorption coating 1111 is inserted downward into the core 210 of the reactor pressure vessel 200, the shutdown control rod carries the liquid metal coolant therein into the core 210, and further, the heat generated by the chain fission reaction of the core 210 is transferred to the liquid metal coolant through the shutdown control rod, causing the liquid metal coolant to absorb the heat and vaporize. The liquid metal coolant absorbs heat generated by the chain fission reaction of the core 210, so that the temperature of the core 210 can be rapidly reduced, and dangerous conditions caused by continuous temperature rise of the core 210 due to waste heat are effectively avoided. Because the shutdown control rod of this application can realize the cooling function of reactor core 210 when realizing the shutdown function, realize the emission of waste heat in the reactor core 210 through this passive system, unusual simple and convenient and the security performance is higher.
In one embodiment, the outer periphery of the shutdown control rod and the direction of insertion into the core 210The end face of the end is coated with the neutron absorption layer, so that the coating area of the neutron absorption layer is large, and the time required for stopping the chain type fission reaction is shorter. When the system receives a shutdown signal sent by the reactor protection system, the total time consumed by the shutdown function is less, and the safety factor of the whole system is higher. Specifically, the neutron absorption coating 1111 is B4Eutectic alloy of C-Al-Si by B4The C-Al-Si eutectic alloy absorbs neutrons in the reactor, stopping the chain fission reaction of the core 210.
Referring to fig. 1, fig. 1 is a schematic diagram illustrating an integrated reactor shutdown and cooling system according to an embodiment of the present invention; FIG. 2 shows an enlarged partial view at A of the integrated reactor shutdown and cooling system shown in FIG. 1; FIG. 4 shows a cross-sectional view at B-B of the integrated reactor shutdown and cooling system shown in FIG. 2.
The structure of the shutdown control rod is described in detail below.
Referring to FIG. 3, in one embodiment, the shutdown control rod includes at least two sections, an evaporation section 111 and a condensation section 113. The evaporation section 111 and the condensation section 113 are connected, and may be integrally formed. The neutron absorption coating 1111 is coated on the outer surface of the evaporation section 111, and the liquid metal coolant is located in the evaporation section 111; the condensing section 113 is arranged above the evaporating section 111, and the condensing section 113 is used for being inserted into the cooling water tank 220; the liquid metal coolant absorbs heat and vaporizes the resulting gas in the evaporator section 111. The gas can rise to the condensing section 113. Since the condensation section 113 is inserted into the cooling water tank 220, the gas reaches the condensation section 113, and then is cooled by the cooling water tank 220, liquefied, and again becomes a liquid metal coolant from a gas state. Specifically, the liquid metal coolant formed by liquefying the gas cooled by the cooling water tank 220 can flow back to the evaporation section 111 under the action of its own gravity, and the heat generated by the chain fission reaction of the core 210 is recycled and absorbed again, so that a closed cycle heat exchange process of the liquid metal coolant inside the shutdown control rod is formed.
In one embodiment, the shutdown control rod further comprises an intermediate section 112, the intermediate section 112 being adapted to connect the evaporator section 111 and the condenser section 113 and being located between the evaporator section 111 and the condenser section 113, such that the gaseous metal coolant rises from the evaporator section 111, passes through the intermediate section 112, and then reaches the condenser section 113. It can be seen that the middle section 112 can extend the flow path of the gaseous metal coolant, so that the gaseous metal coolant has a larger flow space and flow distance, which is more beneficial to the rapid cooling of the core 210.
Referring to fig. 3 and 4, in one embodiment, the shutdown control rod further includes a wick 120; the wick 120 is disposed on an inner wall of the closed cavity 110, the wick 120 serves to absorb the metal coolant that forms a liquid state after being liquefied, and the liquid metal coolant can flow downward through the wick 120. By the absorption of the wick 120, the liquid metal coolant is collected faster in the process of the metal coolant condensing and reflowing, and the time required by the condensing and reflowing is shorter, so that the temperature reduction speed of the core 210 is further increased.
In one embodiment, the liquid metal coolant is liquid sodium, and absorbs heat generated by the chain fission reaction of the core 210 through the liquid sodium, and when gas formed by vaporization of the liquid sodium in the evaporation section 111 rises to the condensation section 113, the gas is cooled by the cooling water tank 220 in the condensation section 113, so that the gas is liquefied to form liquid sodium, and then the liquid sodium is adsorbed onto the wick 120, flows back to the evaporation section 111 through self gravity, and circulates again to absorb heat generated by the chain fission reaction of the core 210.
In another embodiment, the liquid metal coolant is liquid potassium, the liquid potassium absorbs heat generated by the chain fission reaction of the core 210, and when gas formed by vaporization of the liquid potassium in the evaporation section 111 rises to the condensation section 113, the gas is cooled by the cooling water tank 220 in the condensation section 113, so that the gas is liquefied to form liquid potassium, and then the liquid potassium is absorbed onto the wick 120, flows back to the evaporation section 111 by self gravity, and circulates again to absorb heat generated by the chain fission reaction of the core 210. The liquid metal coolant is not limited in kind as long as it can perform the functions of vaporizing at a higher temperature and radiating and liquefying at a lower temperature.
Referring to FIG. 4, in one embodiment, the shutdown control rod is a sealed metal tube for exhausting non-condensable gas, and the material of the rod housing 140 is 316 stainless steel surface nitrided, so that the shutdown control rod 100 has higher safety performance and longer service life.
With continued reference to FIG. 3, in one embodiment, the shutdown control rod further includes a counterweight segment 130 connected to the condenser segment 113 and positioned above the condenser segment 113. Due to the arrangement of the counterweight section 130, the weight of the rod body of the shutdown control rod is increased, and the problem that the reactor density is higher than that of the shutdown control rod is solved. Particularly, when the shutdown control rod is applied to a shutdown and cooling integrated system of a lead-based reactor, the large buoyancy caused by heavy metal lead or lead alloy coolant is overcome, and the safety of the reactor is improved.
The reactor shutdown and cooling integrated system provided by the invention can solve at least one technical problem.
Referring to fig. 1, a reactor shutdown and cooling integrated system according to an embodiment of the present invention includes a reactor pressure vessel 200, a cooling water tank 220, the shutdown control rods 100, and a control rod drive mechanism 240. A reactor core 210 is arranged in the reactor pressure vessel 200, and a cooling water tank 220 is positioned above the reactor core 210; the evaporation section 111 of the shutdown control rod 100 can be inserted into the core 210, and the condensation section 113 of the shutdown control rod 100 can extend into the cooling water tank 220; a control rod drive mechanism 240 is coupled to the shutdown control rod 100, the control rod drive mechanism 240 being configured to move the shutdown control rod 100 along its length.
When the reactor shutdown and cooling integrated system receives a shutdown signal sent by a reactor protection system, one end of the shutdown control rod 100 coated with the neutron absorption coating 1111 enters the reactor core 210 of the reactor pressure vessel 200 through the control rod driving mechanism 240, and the neutron absorption coating 1111 is used for absorbing neutrons to stop the chain fission reaction of the reactor core 210, so that the shutdown function is realized. Because the closed cavity 110 is arranged in the shutdown control rod 100, and the liquid metal coolant is arranged in the closed cavity 110, the liquid metal coolant absorbs heat generated by the chain fission reaction of the reactor core 210, so that the temperature of the reactor core 210 can be rapidly reduced, and dangerous conditions caused by continuous temperature rise of the reactor core 210 due to waste heat are effectively avoided.
Referring to fig. 1, 2 and 4, the reactor shutdown and cooling integrated system according to an embodiment of the present invention further includes a control rod guide sleeve 230, the control rod guide sleeve 230 is connected to the cooling water tank 220 and is located above the core 210, and the shutdown control rods 100 are inserted through the control rod guide sleeve 230. By providing the control rod guide sleeve 230, the shutdown control rod 100 is inserted along the guide sleeve 230 when inserted into the reactor core 210 of the reactor, so that the insertion direction is very accurate, the shutdown control rod 100 is not prone to deformation such as deflection and bending, and the service life of the shutdown control rod 100 is longer.
Referring to fig. 2 and 4, the cooling water tank 220 of the integrated reactor shutdown and cooling system according to an embodiment of the present invention further includes a cooling jacket 221, and the cooling jacket 221 is sleeved outside the control rod guide sleeve 230. Specifically, the cooling jacket 221 is designed in the form of a special-shaped bellows, so that the heat exchange area between the shutdown control rod 100 and the cooling water tank 220 is increased, the heat transfer of the system is enhanced, the heat extraction efficiency of the system is improved, and the accident risk caused by the over-high temperature and slow heat reduction of the reactor core 210 is effectively reduced.
Referring to fig. 1, the reactor shutdown and cooling integrated system according to an embodiment of the present invention further includes a steam pipe 250, and one end of the steam pipe 250 is connected and communicated with the cooling water tank 220. When the cooling water in the cooling water tank 220 absorbs heat released from the evaporation section 111 of the shutdown control rod 100 to reach a saturation temperature, the generated steam can be discharged through the steam pipe 250.
Referring to fig. 1, the reactor shutdown and cooling integrated system according to an embodiment of the present invention further includes a chimney 270, a passive condenser 260, and a cooling water pipeline 300, wherein an arrow E in fig. 1 indicates a direction of air flowing into the chimney 270. Specifically, the passive condenser 260 is connected to the other end of the steam pipe 250, the passive condenser 260 is installed on the chimney 270, one end of the cooling water pipe 300 is connected to the passive condenser 260, and the other end is connected to the cooling water tank 220. The steam that produces in the coolant tank 220 passes through in the steam pipe 250 gets into passive condenser 260, thereby forms rivers through the liquefaction of passive condenser 260 condensation back, thereby this rivers can recycle through inside coolant pipe 300 backward to coolant tank 220. When the passive condenser 260 performs the condensing operation, heat is released to the outside air indicated by an arrow E through a chimney 270.
With continued reference to fig. 1, the reactor shutdown and cooling integrated system according to an embodiment of the present invention further includes a steam isolation valve 280 and a cooling water isolation valve 290. Wherein, arrow C in fig. 1 indicates inside of the containment, arrow D indicates outside of the containment, steam isolation valve 280 is disposed on steam pipeline 250 and outside of the containment, and cooling water isolation valve 290 is disposed on cooling water pipeline 300 and outside of the containment. When the reactor is in a normal working state, the steam isolation valve 280 and the cooling water isolation valve 290 are in a normally closed state, and when the reactor shutdown and cooling integrated system needs to be put into operation, the steam isolation valve 280 and the cooling water isolation valve 290 are opened.
Specifically, the invention is a passive system, the system does not rely on an external power supply under the shutdown working condition, when an emergency shutdown signal occurs, the shutdown control rods 100 can be quickly inserted into the reactor core 210, and the dual functions of shutdown and cooling are realized, at this time, steam generated in the cooling water tank 220 in the cooling process enters the passive condenser 260 through the steam isolation valve 280 on the steam pipeline 250 to be cooled and gathered to form water flow, and finally enters the cooling water tank 220 through the cooling water isolation valve 290 on the cooling water pipe, and because water in the cooling water tank 220 is not consumed when the system works, no requirement is required on the pressure bearing of the containment, the overall design is simplified, and the reliability and the safety of the cooling function of the reactor core 210 are improved. Because the passive condenser 260 is a consumable product, when the passive condenser 260 needs to be replaced or overhauled, the steam isolation valve 280 and the cooling water isolation valve 290 are closed, which is very simple and convenient. In addition, the air outside the containment is used as the heat trap to discharge the waste heat of the reactor core 210, so that the condenser is sensitive in arrangement, high in system adaptability and low in requirement on the external environment, and the requirement of the system on discharging the waste heat for a long time can be met.
According to the reactor shutdown and cooling integrated system provided by the invention, the natural circulation of the liquid metal coolant in the shutdown control rods 100 and the closed circulation of the cooling water loop in the cooling water tank 220 are adopted to discharge the heat of the reactor core 210, so that the contact between the coolant inside the reactor core 210 and the cooling loop is avoided, the problem of environmental pollution caused by radioactive substance leakage inside the reactor core 210 is effectively prevented, and the safety of a power plant is improved.
The technical features of the embodiments described above may be arbitrarily combined, and for the sake of brevity, all possible combinations of the technical features in the embodiments described above are not described, but should be considered as being within the scope of the present specification as long as there is no contradiction between the combinations of the technical features.
The above-mentioned embodiments only express several embodiments of the present invention, and the description thereof is more specific and detailed, but not construed as limiting the scope of the invention. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the inventive concept, which falls within the scope of the present invention. Therefore, the protection scope of the present patent shall be subject to the appended claims.
Claims (10)
1. A shutdown control rod characterized in that the outer surface of the shutdown control rod is coated with a neutron absorbing coating (1111); a closed cavity (110) is arranged in the shutdown control rod, and a liquid metal coolant is arranged in the closed cavity (110); when the shutdown control rod is inserted into the core (210) of the reactor pressure vessel (200), the neutron absorption coating (1111) can absorb neutrons so that the chain fission reaction of the core (210) is stopped, and the liquid metal coolant can absorb heat generated by the chain fission reaction of the core (210) to be vaporized.
2. The shutdown control rod of claim 1, wherein the shutdown control rod comprises at least:
an evaporator section (111), the neutron absorbing coating (1111) being applied to an outer surface of the evaporator section (111), the metal coolant in a liquid state being located within the evaporator section (111); and
the condensation section (113), the condensation section (113) is connected with the evaporation section (111), the condensation section (113) is arranged above the evaporation section (111), and the condensation section (113) is used for being inserted into a cooling water tank (220); the gas formed by the evaporation of the liquid metal coolant in the evaporation section (111) can rise to the condensation section (113), and the gas can be cooled by the cooling water tank (220) in the condensation section (113), so that the liquid metal coolant is liquefied.
3. The shutdown control rod of claim 2 further comprising a wick (120); the liquid absorbing core (120) is arranged on the inner wall of the closed cavity (110), the liquid absorbing core (120) is used for absorbing the liquefied metal coolant, and the liquid metal coolant can flow downwards through the liquid absorbing core (120).
4. The shutdown control rod of claim 3 further comprising a counterweight segment (130), the counterweight segment (130) being connected to and located above the condenser segment (113).
5. An integrated reactor shutdown and cooling system, comprising:
a reactor pressure vessel (200), wherein a reactor core (210) is arranged in the reactor pressure vessel (200);
a cooling water tank (220), the cooling water tank (220) being located above the core (210); and
the shutdown control rod (100) of any one of claims 2 to 4, an evaporator section (111) of the shutdown control rod (100) being insertable into the core (210), a condenser section (113) of the shutdown control rod (100) being extendable into the coolant tank (220).
6. The integrated reactor shutdown and cooling system of claim 5, further comprising a control rod guide sleeve (230), the control rod guide sleeve (230) extending through the cooling water tank (220) and being positioned above the core (210), the shutdown control rods (100) being disposed through the control rod guide sleeve (230).
7. The integrated reactor shutdown and cooling system of claim 6, wherein the cooling water tank (220) further comprises a cooling jacket (221), the cooling jacket (221) being sleeved outside the control rod guide sleeve (230).
8. The integrated reactor shutdown and cooling system of claim 6, further comprising a control rod drive mechanism (240), the control rod drive mechanism (240) being connected to the shutdown control rod (100), the control rod drive mechanism (240) being configured to drive the shutdown control rod (100) to move along the length of the control rod guide sleeve (230).
9. The integrated reactor shutdown and cooling system of claim 6, further comprising a steam pipe (250), wherein one end of the steam pipe (250) is connected and communicated with the cooling water tank (220).
10. The integrated reactor trip and cooling system of claim 9, further comprising:
a chimney (270);
the passive condenser (260), the passive condenser (260) is connected with the other end of the steam pipeline (250), and the passive condenser (260) is installed on the chimney (270); and
a cooling water pipe (300), the cooling water pipe (300) being connected between the passive condenser (260) and the cooling water tank (220).
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CN114420322A (en) * | 2021-11-30 | 2022-04-29 | 中国船舶重工集团公司第七一九研究所 | Passive residual heat removal system |
Citations (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4032401A (en) * | 1972-06-30 | 1977-06-28 | Westinghouse Electric Corporation | Combined solid and liquid system for controlling nuclear reactors |
JPH05196763A (en) * | 1992-01-21 | 1993-08-06 | Central Res Inst Of Electric Power Ind | Core of liquid-metal cooled fast reactor |
JP2004233210A (en) * | 2003-01-30 | 2004-08-19 | Kawasaki Heavy Ind Ltd | Flow rate response type reactor shutdown and drive element and nuclear reactor structure |
CN103474098A (en) * | 2012-06-06 | 2013-12-25 | 中国核动力研究设计院 | Core using machinery control rod combination boron injection system as second reactor shutdown system |
CN109215813A (en) * | 2018-09-13 | 2019-01-15 | 中国核动力研究设计院 | Pressurized-water reactor thimble tube complementary shutdown system and method |
CN109243634A (en) * | 2018-08-27 | 2019-01-18 | 中广核研究院有限公司 | Reactor safety system |
CN110211709A (en) * | 2019-06-14 | 2019-09-06 | 北京卫星环境工程研究所 | Heat pipe-type alkali metal converts integral reactor |
CN210271804U (en) * | 2019-03-06 | 2020-04-07 | 中广核研究院有限公司 | Emergent waste heat discharge system of water injection formula lead bismuth fast reactor |
CN111768881A (en) * | 2020-07-22 | 2020-10-13 | 西安热工研究院有限公司 | Liquid passive reactor control rod and working method thereof |
CN111933314A (en) * | 2020-08-07 | 2020-11-13 | 上海核工程研究设计院有限公司 | Passive shutdown device for nuclear reactor |
-
2021
- 2021-04-28 CN CN202110466343.7A patent/CN113345606B/en active Active
Patent Citations (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4032401A (en) * | 1972-06-30 | 1977-06-28 | Westinghouse Electric Corporation | Combined solid and liquid system for controlling nuclear reactors |
JPH05196763A (en) * | 1992-01-21 | 1993-08-06 | Central Res Inst Of Electric Power Ind | Core of liquid-metal cooled fast reactor |
JP2004233210A (en) * | 2003-01-30 | 2004-08-19 | Kawasaki Heavy Ind Ltd | Flow rate response type reactor shutdown and drive element and nuclear reactor structure |
CN103474098A (en) * | 2012-06-06 | 2013-12-25 | 中国核动力研究设计院 | Core using machinery control rod combination boron injection system as second reactor shutdown system |
CN109243634A (en) * | 2018-08-27 | 2019-01-18 | 中广核研究院有限公司 | Reactor safety system |
CN109215813A (en) * | 2018-09-13 | 2019-01-15 | 中国核动力研究设计院 | Pressurized-water reactor thimble tube complementary shutdown system and method |
CN210271804U (en) * | 2019-03-06 | 2020-04-07 | 中广核研究院有限公司 | Emergent waste heat discharge system of water injection formula lead bismuth fast reactor |
CN110211709A (en) * | 2019-06-14 | 2019-09-06 | 北京卫星环境工程研究所 | Heat pipe-type alkali metal converts integral reactor |
CN111768881A (en) * | 2020-07-22 | 2020-10-13 | 西安热工研究院有限公司 | Liquid passive reactor control rod and working method thereof |
CN111933314A (en) * | 2020-08-07 | 2020-11-13 | 上海核工程研究设计院有限公司 | Passive shutdown device for nuclear reactor |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN114420322A (en) * | 2021-11-30 | 2022-04-29 | 中国船舶重工集团公司第七一九研究所 | Passive residual heat removal system |
CN114420322B (en) * | 2021-11-30 | 2024-05-17 | 中国船舶重工集团公司第七一九研究所 | Passive waste heat discharging system |
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