CN217690506U - Passive reactor core cooling system - Google Patents

Passive reactor core cooling system Download PDF

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Publication number
CN217690506U
CN217690506U CN202220118032.1U CN202220118032U CN217690506U CN 217690506 U CN217690506 U CN 217690506U CN 202220118032 U CN202220118032 U CN 202220118032U CN 217690506 U CN217690506 U CN 217690506U
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valve
reactor core
containment
connecting pipe
vessel
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CN202220118032.1U
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谢小飞
陶俊
梁潇
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Hualong International Nuclear Power Technology Co Ltd
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Hualong International Nuclear Power Technology Co Ltd
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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 present application provides a passive reactor core cooling system, including: the device comprises a containment, a pressure vessel, a first connecting pipe, a second connecting pipe and a heat exchanger arranged outside the containment; the pressure vessel is arranged in the containment vessel and is used for placing a reactor core; a first opening and a second opening are formed in the wall of the containment shell; the outlet of the pressure vessel is communicated with the first end of the first connecting pipe, the second end of the first connecting pipe passes through the first opening to be communicated with the inlet of the heat exchanger, the outlet of the heat exchanger is communicated with the first end of the second connecting pipe, and the second end of the second connecting pipe passes through the second opening to be communicated with the inlet of the pressure vessel. Through continuously exporting the heat of the reactor core in the pressure vessel to the outside of the containment vessel, the reactor core is cooled, and compared with the prior art, the cooling efficiency is higher.

Description

Passive reactor core cooling system
Technical Field
The application relates to the technical field of nuclear power plant safety, in particular to a passive reactor core cooling system.
Background
The nuclear reactor in the nuclear power station is structurally characterized in that a pressure vessel is arranged in a containment vessel, and a reactor core is arranged in the pressure vessel, so that the reactor core can be damaged due to a large amount of decay heat generated by the reactor core under the working condition of accident operation. In order to ensure the safety of the reactor core, the heat generated by the core in the pressure vessel needs to be continuously conducted away. In order to ensure the integrity of the containment vessel, the heat of the containment vessel needs to be conducted out of the containment vessel.
Two passive reactor core cooling modes are provided, one is to cool the secondary side of the steam generator through a secondary side passive waste heat removal system of the steam generator arranged outside the containment vessel, and then to cool a primary loop of the reactor by using the steam generator, so as to cool the reactor core; one is that the heat generated by the reactor core is led out of the pressure vessel to the containment through a passive reactor core cooling system arranged in the containment, and then the heat in the containment is led out of the containment through the containment cooling system, so that the safety of the reactor core and the containment is ensured. The two passive core cooling systems can guide out the heat of the reactor core to the outside of the containment after twice heat exchange, and the efficiency is low.
SUMMERY OF THE UTILITY MODEL
The embodiment of the application provides a passive reactor core cooling system, which can solve the problem of low reactor core cooling efficiency in the prior art.
In order to solve the technical problem, the present application is implemented as follows:
the embodiment of the present application provides a passive reactor core cooling system, includes: the device comprises a containment, a pressure vessel, a first connecting pipe, a second connecting pipe and a heat exchanger arranged outside the containment;
the pressure vessel is arranged in the containment vessel and is used for placing a reactor core;
a first opening and a second opening are formed in the wall of the containment shell;
the outlet of the pressure vessel is communicated with the first end of the first connecting pipe, the second end of the first connecting pipe penetrates through the first opening to be communicated with the inlet of the heat exchanger, the outlet of the heat exchanger is communicated with the first end of the second connecting pipe, and the second end of the second connecting pipe penetrates through the second opening to be communicated with the inlet of the pressure vessel.
Optionally, the inlet of the pressure vessel comprises a reactor cold pipe safety injection interface and a pressure vessel direct injection interface.
Optionally, the system further includes a first pressure relief valve, the first pressure relief valve is located in the containment vessel, and the first pressure relief valve is disposed on the first connection pipe and used for communicating or shutting off the first connection pipe.
Optionally, the system further comprises a voltage stabilizer, wherein the voltage stabilizer is arranged on the first connecting pipe and is located between the first pressure relief valve and the pressure container.
Optionally, the system further includes a first valve and a second valve, the first valve and the second valve are both disposed on the first connection pipe, and the first valve is located between the first pressure relief valve and the second valve;
the first valve is located within the containment vessel and the second valve is located outside the containment vessel.
Optionally, the system further includes a third valve and a fourth valve, the third valve and the fourth valve are both disposed on the second connecting pipe, the third valve is located outside the containment vessel, and the fourth valve is located inside the containment vessel.
Optionally, a condensation water tank is included, the condensation water tank is located at a high position outside the containment vessel, and the heat exchanger is located in the condensation water tank.
Optionally, the first valve, the second valve, the third valve and the fourth valve are all isolation valves.
In the embodiment of the application, high-temperature steam in the pressure vessel enters the heat exchanger through the first connecting pipe to be cooled, and then flows back to the pressure vessel through the second connecting pipe, wherein the pressure vessel is arranged in the containment, the heat exchanger is arranged outside the containment, and the pressure vessel is used for placing the reactor core. Therefore, the reactor core is cooled by continuously leading out the heat of the reactor core in the pressure vessel to the outside of the containment, and compared with the prior art, the cooling efficiency is higher.
Drawings
Fig. 1 is a schematic structural diagram of a passive reactor core cooling system according to an embodiment of the present disclosure.
Detailed Description
The technical solutions in the embodiments of the present application will be clearly and completely described below with reference to the drawings in the embodiments of the present application, and it is obvious that the described embodiments are some, but not all, embodiments of the present application. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present application.
Unless otherwise defined, technical or scientific terms used herein shall have the ordinary meaning as understood by one of ordinary skill in the art to which this application belongs. As used in this application, the terms "first," "second," and the like do not denote any order, quantity, or importance, but rather are used to distinguish one element from another. Also, the use of 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 "coupled" and the like are not restricted to physical or mechanical connections, but may include electrical connections, whether direct or indirect. "upper", "lower", "left", "right", and the like are used only to indicate relative positional relationships, and when the absolute position of the object to be described is changed, the relative positional relationships are changed accordingly.
Referring to fig. 1, fig. 1 is a schematic structural diagram of a passive reactor core cooling system according to an embodiment of the present disclosure, where the system includes: a containment vessel, a pressure vessel 10, a first connecting pipe 20, a second connecting pipe 30, and a heat exchanger 40 disposed outside the containment vessel;
the pressure vessel 10 is arranged in the containment vessel, and the pressure vessel 10 is used for placing a reactor core;
a first opening and a second opening are formed in the wall of the containment shell;
the outlet of the pressure vessel 10 is communicated with the first end of the first connection pipe 20, the second end of the first connection pipe 20 is communicated with the inlet of the heat exchanger 40 through the first opening, the outlet of the heat exchanger 40 is communicated with the first end of the second connection pipe 30, and the second end of the second connection pipe 30 is communicated with the inlet of the pressure vessel 10 through the second opening.
The system is used as a backup of a secondary side heat removal system under a design reference accident, and is in a standby state under the condition of normal power operation of a nuclear power station. Specifically, the system is applied to the design expansion working condition that a primary loop is intact but a secondary side heat removal system is unavailable, and continuously discharges the waste heat of the reactor core in a passive mode, so that the long-term cooling of the reactor core is ensured, and the reactor core is prevented from being melted.
In the embodiment of the present application, high-temperature steam in the pressure vessel 10 enters the heat exchanger 40 through the first connection pipe 20 to be cooled, and then flows back to the pressure vessel 10 through the second connection pipe 30, wherein the pressure vessel 10 is disposed in a containment, the heat exchanger 40 is disposed outside the containment, and the pressure vessel 10 is used for placing a reactor core. Therefore, the reactor core is cooled by continuously guiding the heat of the reactor core in the pressure vessel 10 out of the containment, and compared with the prior art, the cooling efficiency is higher by cooling the outer surface of the pressure vessel 10.
Wherein, this heat exchanger 40 can be C type heat exchanger, and its heat exchange efficiency is high.
Optionally, the inlet of the pressure vessel 10 includes a reactor cold pipe safety injection port and a pressure vessel direct injection port. Optionally, the system further includes a voltage stabilizer 50, the voltage stabilizer 50 is disposed on the first connecting tube 20, and the voltage stabilizer 50 is located in the safety shell.
In an implementation, the pressurizer 50 is a device that stabilizes the loop pressure during normal plant operation. The regulator 50 is an important component of the cooling circuit during operation of the system.
Optionally, the system further comprises a first pressure relief valve 60 disposed on top of the pressure stabilizer 50, wherein the first pressure relief valve 60 is used for connecting or disconnecting the first connection pipe 20. Wherein, the quantity of first pressure relief valve 60 can be two, and two first pressure relief valves 60 are parallelly connected to be set up, through setting up two first pressure relief valves 60 to improve the reliability of system.
In specific implementation, under the condition of an accident condition, an operator judges according to the state of a power plant, when heat extraction on the secondary side of a steam generator is required to be started but the starting fails, the first pressure relief valve 60 is opened, and the first valve, the second valve, the third valve and the fourth valve are opened according to the sequence, at the moment, the first connecting pipe 20 and the second connecting pipe 30 are in a communicated state, and heat in the pressure container 10 enters the heat exchanger 40 through the voltage stabilizer 50 and the first connecting pipe 20 to be cooled; when the secondary side heat rejection system is available, the first pressure relief valve 60 is in a closed state and the system is not in use.
In another alternative embodiment, the first pressure relief valve 60 may be an automatic pressure relief valve, and when it is detected that the steam generator secondary side heat rejection system needs to be started but fails, the first pressure relief valve 60 is opened and the system starts to operate. By setting the first pressure relief valve 60 as an automatic pressure relief valve, the operation state of the secondary side heat extraction system is monitored, and the switch of the system is controlled, so that the situation that an operator mistakenly starts the equipment or the starting time is untimely is avoided, and the automation degree of the system is improved.
Optionally, the system further comprises a first valve 21 and a second valve 22, wherein the first valve 21 and the second valve 22 are both disposed on the first connecting pipe 20, and the first valve 21 is located between the first pressure relief valve 60 and the second valve 22;
the first valve 21 is located inside the containment vessel and the second valve 22 is located outside the containment vessel.
In this embodiment, two valves are disposed on the first connecting pipe 20, and the two valves are respectively located at two sides of the containment, so that the system can still operate when the valve at one side is damaged, and the reliability of the system operation can be improved compared with one valve.
Optionally, the system further includes a third valve 31 and a fourth valve 32, the third valve 31 and the fourth valve 32 are both disposed on the second connecting pipe 30, the third valve 31 is located outside the containment vessel, and the fourth valve 32 is located inside the containment vessel.
In this embodiment, two valves are disposed on the second connecting pipe 30, and the two valves are respectively located at two sides of the containment, so that the system can still operate when the valve at one side is damaged, and the reliability of the system operation can be improved compared with one valve.
Optionally, the first valve 21, the second valve 22, the third valve 31 and the fourth valve 32 are isolation valves.
The isolation valve belongs to a switch valve, is only in an open state or a closed state, and is different from the switch valve in that the isolation valve basically has requirements on leakage grade, so that the isolation valve is widely applied to safety facilities of a nuclear power plant. The safety requirement is relatively higher than that of a switch valve, and some parts have higher requirements on opening and closing speed. It should be said that a valve emphasizes two-sided fluid separation and greater safety.
Optionally, a condensed water tank 70 is included, the condensed water tank 70 is located at the high level outside the containment vessel, and the heat exchanger 40 is located in the condensed water tank 70.
The condensed water tank 70 should have a certain height difference with the pressure vessel 10, so that the cooling water formed by cooling through the heat exchanger 40 can flow back into the pressure vessel 10 in a passive manner without the aid of a power supply or other equipment.
In this embodiment, the condensed water tank 70 is provided to cool the fluid in the heat exchanger 40 after absorbing heat.
Optionally, the system further includes a pressure relief tank and a third connection pipe, the pressure relief tank and the third connection pipe are both disposed in the containment, and the third connection pipe connects the pressure relief tank and the pressure stabilizer.
The pressure relief tank is a container that receives and cools steam and/or water discharged from the pressurizer, safety valves of a waste heat removal system, safety valves of a chemical and volume control system, and the like.
Optionally, the system still includes the second relief valve, the second relief valve sets up on the third connecting pipe for communicate or turn-off the third connecting pipe.
While the present embodiments have been described with reference to the accompanying drawings, the present embodiments are not limited to the above-described embodiments, which are merely illustrative and not restrictive, and it will be apparent to those of ordinary skill in the art that many more modifications and variations can be made without departing from the spirit and scope of the invention as defined in the appended claims.

Claims (7)

1. A passive reactor core cooling system, comprising: the device comprises a containment, a pressure vessel, a first connecting pipe, a second connecting pipe and a heat exchanger arranged outside the containment;
the pressure vessel is arranged in the containment vessel and is used for placing a reactor core;
a first opening and a second opening are formed in the shell wall of the containment shell;
the outlet of the pressure vessel is communicated with the first end of the first connecting pipe, the second end of the first connecting pipe passes through the first opening to be communicated with the inlet of the heat exchanger, the outlet of the heat exchanger is communicated with the first end of the second connecting pipe, and the second end of the second connecting pipe passes through the second opening to be communicated with the inlet of the pressure vessel.
2. The passive reactor core cooling system of claim 1, wherein the inlet of the pressure vessel comprises a reactor cold pipe safety injection interface and a pressure vessel direct injection interface.
3. The passive reactor core cooling system of claim 1, further comprising a pressurizer disposed on the first connection tube, the pressurizer located within the containment vessel.
4. The passive reactor core cooling system of claim 3, further comprising a first pressure relief valve disposed at a top of the pressurizer, the first pressure relief valve being configured to open or close the first connection pipe.
5. The passive reactor core cooling system of claim 4, further comprising a first valve and a second valve, the first valve and the second valve each disposed on the first connection tube, and the first valve positioned between the first pressure relief valve and the second valve;
the first valve is located within the containment vessel and the second valve is located outside the containment vessel.
6. The passive reactor core cooling system according to claim 5, further comprising a third valve and a fourth valve, the third valve and the fourth valve both disposed on the second connecting tube, and the third valve located outside the containment vessel and the fourth valve located inside the containment vessel.
7. The passive reactor core cooling system according to claim 1, comprising a condensate tank located at an elevated location outside the containment vessel, the heat exchanger being located within the condensate tank.
CN202220118032.1U 2022-01-17 2022-01-17 Passive reactor core cooling system Active CN217690506U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202220118032.1U CN217690506U (en) 2022-01-17 2022-01-17 Passive reactor core cooling system

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202220118032.1U CN217690506U (en) 2022-01-17 2022-01-17 Passive reactor core cooling system

Publications (1)

Publication Number Publication Date
CN217690506U true CN217690506U (en) 2022-10-28

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Family Applications (1)

Application Number Title Priority Date Filing Date
CN202220118032.1U Active CN217690506U (en) 2022-01-17 2022-01-17 Passive reactor core cooling system

Country Status (1)

Country Link
CN (1) CN217690506U (en)

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