CN219202771U - Safe injection system and nuclear power system - Google Patents
Safe injection system and nuclear power system Download PDFInfo
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- CN219202771U CN219202771U CN202320160190.8U CN202320160190U CN219202771U CN 219202771 U CN219202771 U CN 219202771U CN 202320160190 U CN202320160190 U CN 202320160190U CN 219202771 U CN219202771 U CN 219202771U
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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 embodiment of the application provides a safety injection system and a nuclear power system, the nuclear power system comprises a containment, a reactor pressure vessel and a reactor coolant system, the reactor pressure vessel and the reactor coolant system are both located in the containment, the reactor coolant system is communicated with the pressure vessel, the safety injection system spans the containment, the safety injection system comprises at least two safety injection subsystems, each safety injection subsystem comprises a first safety injection tank, the first safety injection tank is communicated with the reactor coolant system through a first pipeline, the first safety injection tank is used for storing boron-containing water, and the pressure at a break of the reactor coolant system is greater than or equal to a first preset pressure value and is less than or equal to a second preset pressure value, and the pressure is input to the reactor coolant system. Thus, by inputting the boron-containing water in the first injection tank to the reactor coolant system, costs can be saved and reliability can be improved as compared with an injection pump having a higher head.
Description
Technical Field
The application relates to the technical field of nuclear power, in particular to a safe injection system and a nuclear power system.
Background
Pressurized water reactor nuclear power plant nuclear power systems typically have a reactor coolant system in which a flowing medium in the reactor coolant absorbs heat from the reactor core and non-radioactive water is heated by a steam generator to produce steam to propel a turbine generator to generate electricity, while the flowing medium in the reactor coolant controls the temperature of the reactor core. In the case of a break or fracture in the reactor coolant system pipe, coolant (e.g., boron-containing water) needs to be injected into the reactor core through the safety injection system to cool and depressurize the reactor coolant system to a safe state, so as to prevent the reactor core from being damaged.
Currently, the safety injection system is to inject the coolant into the reactor core through the reactor coolant system by arranging the safety injection pump, and in the case that the break of the primary loop pipeline is smaller, at this time, the pressure at the break of the pipeline of the reactor coolant system is larger, and the safety injection pump with a very high pressure head is required to be arranged to inject the coolant into the reactor core. However, the high head pump is not the most reliable and costly.
Disclosure of Invention
The embodiment of the application provides a safe injection system and a nuclear power system, which are used for solving the problem of high cost due to the fact that an safe injection pump with a high pressure head is arranged in the related technology.
In order to solve the technical problems, the application is realized as follows:
in a first aspect, an embodiment of the present application provides a safety injection system, applied to a nuclear power system, where the nuclear power system includes a containment vessel, a reactor pressure vessel, and a reactor coolant system, where the reactor pressure vessel is used for placing a reactor core, the reactor pressure vessel and the reactor coolant system are both located in the containment vessel, the reactor coolant system is in communication with the reactor pressure vessel, the safety injection system spans the inside and outside of the containment vessel, the safety injection system includes at least two columns of safety injection subsystems, each column of safety injection subsystem includes a first safety injection tank, the first safety injection tank is in communication with the reactor coolant system, the first safety injection tank is used for storing boron-containing water, and the boron-containing water in the first safety injection tank is used for being input to the reactor coolant system when a pressure at a break of the reactor coolant system is greater than or equal to a first preset pressure value and less than or equal to a second preset pressure value.
Optionally, each column of the safety injection subsystem further comprises a second safety injection tank, the first safety injection tank is communicated with the reactor coolant system through a first pipeline, and the second safety injection tank is communicated with the reactor coolant system through a second pipeline;
the boron-containing water in the first safety injection tank is used for being input into the reactor coolant system when the pressure at the break of the reactor coolant system is greater than or equal to the first preset pressure value and less than or equal to the second preset pressure value;
the boron-containing water in the second safety injection tank is used for being input into the reactor coolant system when the pressure at the break of the reactor coolant system is larger than or equal to a third preset pressure value and smaller than the first preset pressure value;
the third preset pressure value is smaller than the first preset pressure value, and the first preset pressure value is smaller than the second preset pressure value.
Optionally, the first pipeline is provided with a first valve, and the second pipeline is provided with a second valve;
opening the first valve when it is detected that the pressure at the break of the reactor coolant system is greater than or equal to the first preset pressure value and less than or equal to the second preset pressure value;
and opening the second valve when the pressure at the break of the reactor coolant system is detected to be greater than or equal to a third preset pressure value and less than the first preset pressure value.
Optionally, the reactor coolant system comprises a plurality of identically configured loops, each loop in communication with at least one column of the safety injection subsystem.
Optionally, each loop includes a steam generator, a first pump body, a cold pipe section, a transition section and a hot pipe section, wherein the first pump body is communicated with the reactor pressure vessel through the cold pipe section, the steam generator is communicated with the reactor pressure vessel through the hot pipe section, and the first pump body is communicated with the steam generator through the transition section;
the first pipe and the second pipe are both communicated with the cold pipe section of the loop.
Optionally, a first penetrating member and a second penetrating member are arranged on the containment wall, the safety injection subsystem further comprises a third pipeline, one end of the third pipeline is communicated with an outlet of the built-in charge water tank in the containment through the first penetrating member, and the other end of the third pipeline is communicated with a cold pipe section of the loop through the second penetrating member.
Optionally, each loop further comprises a second pump body and a heat exchanger, wherein the second pump body and the heat exchanger are arranged outside the containment, the inlet end of the second pump body is communicated with the third pipeline, the outlet end of the second pump body is communicated with the inlet end of the heat exchanger, and the outlet end of the heat exchanger is communicated with the cold pipe section.
Optionally, the reactor coolant system further comprises a pressurizer in communication with the plurality of loops.
Optionally, the first safety tank has a level higher than the level of each device in the reactor coolant system.
In a second aspect, embodiments of the present application provide a nuclear power system comprising a safety injection system as described in the first aspect.
In this embodiment of the application, this safety injection system is applied to nuclear power system, the nuclear power system includes containment, reactor pressure vessel and reactor coolant system, the reactor pressure vessel is used for placing the reactor core, the reactor pressure vessel with the reactor coolant system is all located in the containment, the reactor coolant system with the reactor pressure vessel is linked together, the safety injection system strides across inside and outside the containment, the safety injection system includes two at least safety injection subsystems, and every safety injection subsystem that listed as all includes a first safety injection case, first safety injection case pass through first pipeline with the reactor coolant system intercommunication, first safety injection case is used for storing the boron-containing water, the boron-containing water in the first safety injection case is used for when the pressure of reactor coolant system's rupture department is greater than or equal to first preset pressure value, and is less than or equal to second preset pressure value the pressure value input to the reactor coolant system. In this way, the boron-containing water in the first injection tank is input into the reactor coolant system to cool the reactor core in the reactor pressure vessel, so that the reaction rate of the reactor core is reduced, and compared with the injection pump with a high pressure head in the related art, the cost can be saved.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present application, the drawings that are needed in the description of the embodiments of the present application will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present application, 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 structural diagram of a safety injection system according to an embodiment of the present application.
FIG. 2 is a schematic diagram of a safety injection system provided in the related art;
Detailed Description
The following description of the embodiments of the present application will be made clearly and fully with reference to the accompanying drawings, in which it is evident that the embodiments described are some, but not all, of the embodiments of the present application. All other embodiments, which can be made by one of ordinary skill in the art based on the embodiments herein without making any inventive effort, are intended to be within the scope of the present application.
Unless defined otherwise, technical or scientific terms used herein should be given the ordinary meaning as understood by one of ordinary skill in the art to which this application pertains. The terms "first," "second," and the like, as used herein, do not denote any order, quantity, or importance. But merely to distinguish between different components. Likewise, the terms "a" or "an" and the like do not denote a limitation of quantity, but rather denote the presence of at least one. The terms "connected" or "connected," and the like, are not limited to physical or mechanical connections, but may include electrical connections, whether direct or indirect. "upper", "lower", "left", "right", etc. are used merely to indicate a relative positional relationship, which changes accordingly when the absolute position of the object to be described changes.
Referring to fig. 1, fig. 1 is a schematic structural diagram of a safety injection system provided in an embodiment of the present application, applied to a nuclear power system, where the nuclear power system includes a containment vessel, a reactor pressure vessel 10, and a reactor coolant system, where the reactor pressure vessel 10 is used for placing a reactor core, the reactor pressure vessel 10 and the reactor coolant system are both located in the containment vessel, the reactor coolant system is in communication with the reactor pressure vessel 10, the safety injection system spans the inside and outside of the containment vessel, the safety injection system includes at least two rows of safety injection subsystems 20, each row of safety injection subsystems 20 includes a first safety injection tank 21, the first safety injection tank 21 is in communication with the reactor coolant system through a first pipe 30, the first safety injection tank 21 is used for storing boron-containing water, and the boron-containing water in the first safety injection tank 21 is used for inputting the boron-containing water into the reactor coolant system when the pressure at a break of the reactor coolant system is greater than or equal to a first preset pressure value and less than or equal to a second preset pressure value.
It should be understood that the reactor coolant system may also be referred to as a circuit system, consisting of a pump body, a steam generator, and associated piping. Consists of a plurality of identical sub-cooling systems according to the capacity thereof, and each sub-cooling system is provided with a steam generator, a pump body and is communicated with the reactor pressure vessel 10 through a pipe. The heat generated in the reactor is carried out when the nuclear power plant operates at normal power, and is transmitted to a secondary loop working medium through a steam generator to generate steam so as to drive a steam turbine generator to generate electricity; in addition, the cooling system operates at high temperature and high pressure, and the equipment and the pipelines form a pressure boundary, so that the cooling system is an important barrier for preventing radioactivity from leaking.
It should be appreciated that providing the first safety injection tank 21 with the boron-containing water, injecting the boron-containing water into the reactor pressure vessel 10 in which the reactor core is disposed, may reduce the fission reaction of the reactor core.
It should be understood that the first preset pressure value and the second preset pressure value are preset pressure values, for example: the first preset pressure value is 50MPa, and the second preset pressure value is 110MPa.
In this embodiment, the safety injection system is applied to a nuclear power system, the nuclear power system includes a containment vessel, a reactor pressure vessel 10 and a reactor coolant system, the reactor pressure vessel 10 is used for placing a reactor core, the reactor pressure vessel 10 and the reactor coolant system are both located in the containment vessel, the reactor coolant system is communicated with the reactor pressure vessel 10, the safety injection system spans the inside and outside of the containment vessel, the safety injection system includes at least two rows of safety injection subsystems 20, each row of safety injection subsystems 20 includes a first safety injection tank 21, the first safety injection tank 21 is communicated with the reactor coolant system through a first pipeline 30, the first safety injection tank 21 is used for storing boron-containing water, and the boron-containing water in the first safety injection tank 21 is used for being input to the reactor coolant system when the pressure at a break of the reactor coolant system is greater than or equal to a first preset pressure value and less than or equal to a second preset pressure value. In this way, by inputting the boron-containing water in the first safety injection tank 21 to the reactor coolant system to cool the reactor core in the reactor pressure vessel 10, the reaction rate of the reactor core is reduced, and costs can be saved as compared with the related art in which the safety injection pump with a high head is provided.
Optionally, each column of the safety injection subsystem 20 further includes a second safety injection tank 22, the second safety injection tank 22 being in communication with the reactor coolant system via a second conduit 40;
the boron-containing water in the first safety injection tank 21 is used for being input to the reactor coolant system when the pressure at the break of the reactor coolant system is greater than or equal to the first preset pressure value and less than or equal to the second preset pressure value;
the boron-containing water in the second safety injection tank 22 is used for being input into the reactor coolant system when the pressure at the break of the reactor coolant system is greater than or equal to a third preset pressure value and less than the first preset pressure value;
the third preset pressure value is smaller than the first preset pressure value, and the first preset pressure value is smaller than the second preset pressure value.
It should be appreciated that the third preset pressure value is a preset pressure value, for example: the third preset pressure value is 20MPa.
In this embodiment, by further providing a second safety injection tank 22 in each safety injection subsystem 20, the first safety injection tank 21 and the second safety injection tank 22 are respectively used for conveying the boron-containing water inside the safety injection tanks into the reactor pressure vessel 10 through the cooling system under the condition that different pressure values at the break are detected, so as to prevent the reactor in the reactor pressure vessel 10 from continuing to react.
In a specific implementation, in the case that the pipeline break of the cooling system is small, at this time, the pressure value at the break is large, and when the pressure value at the break is detected to be less than or equal to the first preset pressure value and less than or equal to the second preset pressure value, the reactor coolant system conveys the boron-containing water into the reactor pressure vessel 10 after conveying the boron-containing water in the first injection tank 21 into the reactor coolant system, so as to prevent the reactor core in the reactor pressure vessel 10 from continuing to react. Wherein the first preset pressure value can be 50MPa and the second preset pressure value is 110MPa.
In the case of a larger break in the reactor coolant system piping, the pressure value at the break is smaller at this time, and after detecting that the pressure value at the break is greater than or equal to the third preset pressure value, and less than the first preset pressure value, the reactor coolant system delivers the boron-containing water in the second safety injection tank 22 into the reactor pressure vessel 10 after delivering the boron-containing water in the reactor coolant system to prevent the reactor core in the reactor pressure vessel 10 from continuing to react, wherein the first preset pressure value may be 50MPa, and the third preset pressure value may be 20MPa.
In addition, the first safety injection tank 21 and the second safety injection tank 22 can be set to supply the boron-containing water in a passive mode, specifically, the horizontal setting height of the first safety injection tank 21 and the second safety injection tank 22 can be set to be higher than the horizontal setting height of each device and each pipeline in the reactor coolant system, and the horizontal setting height of the first safety injection tank 21 is higher than the horizontal setting height of the second safety injection tank 22; the first safety injection tank 21 may be provided to supply the boron-containing water in a passive manner, and the second safety injection tank 22 may be provided to supply the boron-containing water in a pressure manner, and specifically, the second safety injection tank 22 may be provided to perform pressure transportation by a gas, wherein the gas may be nitrogen, air, or the like, and the present embodiment is not limited thereto.
Optionally, the first pipe 30 is provided with a first valve 31, and the second pipe 40 is provided with a second valve 41;
opening the first valve when it is detected that the pressure at the break of the reactor coolant system is greater than or equal to the first preset pressure value and less than or equal to the second preset pressure value;
and opening the second valve when the pressure at the break of the reactor coolant system is detected to be greater than or equal to a third preset pressure value and less than the first preset pressure value.
It should be appreciated that the first valve 31 and the second valve 41 are both pressure regulating valves.
In the present embodiment, the opening of the first safety injection tank 21 or the second safety injection tank 22 is controlled by providing pressure regulating valves in both the first pipe 30 connecting the first safety injection tank 21 with the reactor coolant system and the second pipe 40 connecting the second safety injection tank 22 with the reactor coolant system, and the pressure regulating valves are controlled to be opened and closed according to the detected pressure values.
Optionally, the reactor coolant system includes a plurality of identically configured loops 50, each loop 50 being in communication with at least one column of the safety injection subsystem 20.
It should be appreciated that the number of loops 50 is related to the reaction capacity, and that each loop 50 is provided in communication with at least one row of safety injection subsystems 20, such that in the event of a breach of a conduit of one of the loops 50, boron-containing water is delivered to the loop 50 via at least one row of safety injection subsystems 20 and then into the reactor pressure vessel 10 to prevent further reaction of the reactor core within the reactor pressure vessel 10.
Optionally, each loop 50 includes a steam generator 51, a first pump body 52, a cold pipe section, a transition section, and a hot pipe section, the first pump body 52 being in communication with the reactor pressure vessel 10 through the cold pipe section, the steam generator 51 being in communication with the reactor pressure vessel 10 through the hot pipe section, the first pump body 52 being in communication with the steam generator 51 through the transition section;
the first conduit 30 and the second conduit 40 are both in communication with the cold leg of the loop 50.
Optionally, a first penetrating member and a second penetrating member are disposed on the containment wall, the safety injection subsystem 20 further includes a third pipe 23, one end of the third pipe 23 is communicated with the outlet of the internal charge water tank in the containment through the first penetrating member, and the other end of the third pipe 23 is communicated with the cold pipe section of the loop 50 through the second penetrating member.
It should be appreciated that the internal refueling water tank is a boron-containing water storage container disposed within the containment vessel and integral with its internal structure for filling the refueling water tank with water during normal operation to safely refuel, low pressure safety injection under accident conditions, and/or a source of containment vessel spray.
Optionally, each column of the safety injection subsystem 20 further comprises a second pump body 24 and a heat exchanger 25 arranged outside the containment, an inlet end of the second pump body 24 is in communication with the third pipe 23, an outlet end of the second pump body 24 is in communication with an inlet end of the heat exchanger 25, and an outlet end of the heat exchanger 25 is in communication with the cold pipe section.
Optionally, the reactor coolant system further comprises a pressurizer 60, the pressurizer 60 being in communication with any loop 50 of the plurality of loops 50.
It should be appreciated that the primary function of the pressurizer 60 is to maintain the pressure of the cooling water (e.g., boron containing water) in the reactor coolant system against overpressure. Specifically, the upper half of the pressure stabilizer 60 is a vapor space, and the lower half is filled with water. The top of the pressure stabilizer 60 is provided with a spray nozzle, and the bottom is provided with an electric heater. The water level in the regulator 60 and the pressure of the primary circuit can be regulated and controlled by controlling the operation of the heater and shower water in the regulator 60. The water level within the regulator 60 is controlled by a set of sophisticated systems to ensure that the regulator 60 will operate properly in the event of a change in reactor power or transient conditions. When the pressure is reduced, the system automatically starts the electric heater to increase steam; when the pressure rises, water is sprayed from the top of the pressure stabilizer 60 to condense the steam into water to reduce the pressure. In addition, the control system also provides a protection signal to cause the reactor to automatically shut down in the event of excessive or excessive low pressure within the pressure regulator 60.
Optionally, the first safety tank 21 is higher in level than the devices in the reactor coolant system.
In this embodiment, by setting the horizontal setting height of the first safety injection tank 21 to be smaller than the horizontal setting height of each device in the reactor coolant system, the first safety injection tank 21 delivers the boron-containing water to the reactor coolant system through the first pipe 30 in a passive manner with the first valve 31 opened, and then to the reactor pressure vessel 10, so as to prevent the reactor core from continuing to react.
In contrast to the related art, as shown in fig. 2, each loop 50 is provided with an injection tank, and each column line takes water from the internal refueling water tank when performing the injection function, and injects boron-containing water into the cold leg of the reactor coolant through the respective pump and heat exchanger 25, and simultaneously into the cold leg and the hot leg of the reactor coolant system during the long-term recirculation injection phase. When the waste heat discharging function is executed, the injection pump takes water from the hot section of the reactor coolant system, and returns to the cold section of the reactor coolant system after being cooled by the heat exchanger. The safety injection box is injected into the cold section of the reactor coolant system through the safety injection pipeline when the pressure of the reactor coolant system is lower than the injection pressure setting value.
Under the design reference working condition, the safety injection system injects the containment built-in material-changing water tank and the boron-containing water in the safety injection tank into the reactor coolant system to participate in the reactivity control. The built-in material-replacing water tank is used as a heat trap in the containment, absorbs heat in the atmosphere of the containment, limits the temperature and pressure of the containment to exceed limit values, and ensures the integrity of the containment. The safety injection system pipeline is provided with a safety shell isolating valve penetrating through the safety shell part to prevent radioactive substances from being released to the environment.
Under the working condition of water loss accident at break, boron-containing water is injected into the reactor core to prevent the reactor core from being exposed and quickly submerging the reactor core again, so as to limit the peak value of the temperature of fuel cladding. And in the accident-controllable state, the boron-containing water is injected into the reactor core for a long time, so that the long-term cooling of the reactor core is realized.
Under the working condition of non-break water loss accident, the effective cooling function of the reactor core is ensured by filling and compensating the shrinkage of the coolant caused by excessive cooling.
In the accident working condition that the water level of the pressure stabilizer 60 can be maintained, the injection pump takes water from the reactor coolant hot section, returns to the reactor coolant cold section after being cooled by the heat exchanger 25, and the core waste heat under the accident working condition is led out.
In the long-term circulation cooling stage, the heat exchanger 25 cools the water in the internal refueling water tank to continuously lead the heat of the reactor core out of the containment, so that the temperature and the pressure in the containment are limited, and the integrity of the containment is ensured.
During normal operation of the plant, the infusion pump and heat exchanger 25 performs a normal waste heat removal function.
The present application also provides a nuclear power system including the above-described safety injection subsystem 20. Because the technical solution of the present embodiment includes all the technical solutions of the foregoing embodiments, at least all the technical effects of the foregoing embodiments can be achieved, which is not described herein in detail.
The foregoing is merely specific embodiments of the present application, but the scope of the present application is not limited thereto, and any person skilled in the art can easily think about changes or substitutions within the technical scope of the present application, and the changes or substitutions are intended to be covered by the scope of the present application. Therefore, the protection scope of the present application shall be subject to the protection scope of the claims.
Claims (10)
1. The utility model provides a safe injection system, is applied to nuclear power system, the nuclear power system includes containment, reactor pressure vessel and reactor coolant system, the reactor pressure vessel is used for placing the reactor core, reactor pressure vessel with the reactor coolant system is all located in the containment, reactor coolant system with reactor pressure vessel is linked together, characterized in that, safe injection system is spanned inside and outside the containment, safe injection system includes at least two safe injection subsystem of train, and every safe injection subsystem of train all includes a first safe injection case, first safe injection case is through first pipeline with reactor coolant system intercommunication, first safe injection case is used for storing boron-containing water, the boron-containing water in the first safe injection case is used for when the pressure of reactor coolant system's rupture department is greater than or equal to first preset pressure value, and is less than or equal to second preset pressure value the pressure value is input to the reactor coolant system.
2. The system of claim 1, wherein each column of said safety injection subsystem further comprises a second safety injection tank, said second safety injection tank being in communication with said reactor coolant system via a second conduit;
the boron-containing water in the first safety injection tank is used for being input into the reactor coolant system when the pressure at the break of the reactor coolant system is greater than or equal to the first preset pressure value and less than or equal to the second preset pressure value;
the boron-containing water in the second safety injection tank is used for being input into the reactor coolant system when the pressure at the break of the reactor coolant system is larger than or equal to a third preset pressure value and smaller than the first preset pressure value;
the third preset pressure value is smaller than the first preset pressure value, and the first preset pressure value is smaller than the second preset pressure value.
3. The system of claim 2, wherein the first conduit is provided with a first valve and the second conduit is provided with a second valve;
opening the first valve when it is detected that the pressure at the break of the reactor coolant system is greater than or equal to the first preset pressure value and less than or equal to the second preset pressure value;
and opening the second valve when the pressure at the break of the reactor coolant system is detected to be greater than or equal to a third preset pressure value and less than the first preset pressure value.
4. The system of claim 3, wherein the reactor coolant system comprises a plurality of identically configured loops, each loop in communication with at least one column of the safety injection subsystem.
5. The system of claim 4, wherein each of said loops includes a steam generator, a first pump body, a cold leg, a transition section, and a hot leg, said first pump body being in communication with said reactor pressure vessel through said cold leg, said steam generator being in communication with said reactor pressure vessel through said hot leg, said first pump body being in communication with said steam generator through said transition section;
the first pipe and the second pipe are both communicated with the cold pipe section of the loop.
6. The system of claim 5, wherein the containment wall is provided with a first penetration and a second penetration, and wherein the safety injection subsystem further comprises a third conduit having one end in communication with the outlet of the internal charge water tank within the containment via the first penetration and the other end in communication with the cold leg of the loop via the second penetration.
7. The system of claim 6, wherein each of the loops further comprises a second pump body and a heat exchanger disposed outside the containment, an inlet end of the second pump body in communication with the third conduit, an outlet end of the second pump body in communication with an inlet end of the heat exchanger, and an outlet end of the heat exchanger in communication with the cold leg.
8. The system of claim 4, wherein the reactor coolant system further comprises a pressurizer in communication with the plurality of loops.
9. The system of claim 2, wherein the first safety tank is at a level higher than the level of each device in the reactor coolant system.
10. A nuclear power system comprising a safety injection system as claimed in any one of claims 1 to 9.
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| CN202320160190.8U CN219202771U (en) | 2023-01-19 | 2023-01-19 | Safe injection system and nuclear power system |
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| CN202320160190.8U CN219202771U (en) | 2023-01-19 | 2023-01-19 | Safe injection system and nuclear power system |
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| GR01 | Patent grant | ||
| GR01 | Patent grant |