CN110097982B - Safe injection and waste heat discharge system of nuclear power plant - Google Patents
Safe injection and waste heat discharge system of nuclear power plant Download PDFInfo
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- CN110097982B CN110097982B CN201910384350.5A CN201910384350A CN110097982B CN 110097982 B CN110097982 B CN 110097982B CN 201910384350 A CN201910384350 A CN 201910384350A CN 110097982 B CN110097982 B CN 110097982B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
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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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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention belongs to the technical field of nuclear safety control, and relates to a safety injection and waste heat discharge system for a nuclear power plant. The system comprises a high-pressure safety injection tank injection loop, a safety injection pump injection loop and a reactor pressure vessel. The system can ensure the safety of the nuclear power plant when the reactor has an accident, greatly improve the safety of the nuclear power plant, and simultaneously give consideration to the function of a waste heat discharge system when the reactor is started and stopped, thereby greatly saving the investment of the nuclear power plant and improving the economy of the nuclear power plant.
Description
Technical Field
The invention belongs to the technical field of nuclear safety control, and relates to a safety injection and waste heat discharge system for a nuclear power plant.
Background
The safety injection system belongs to a safety facility specially designed for a nuclear power plant, and when a reactor coolant system has a loss of coolant accident or a main steam system has a pipeline rupture or other accidents, the safety injection system can complete the emergency cooling function of a reactor core, prevent the reactor core from being melted down and ensure the safety of the nuclear power plant. The system is only used when an accident occurs in the nuclear power plant.
There are some reports in the prior art regarding safety infusion systems.
For example, chinese patent application 201310301651.X discloses a passive safety injection system using a safety injection tank. The passive safety injection system comprises: a containment vessel; a reactor mounted in a containment; a safety injection tank mounted in the containment vessel; a safety injection line between the reactor or the reactor coolant system and each safety injection tank to guide water stored in the safety injection tank into the reactor when a water level in the reactor is lowered due to occurrence of a coolant loss accident; and a pressure equalization line between the reactor or the reactor coolant system and the safety injection tank to direct high temperature steam from the reactor to the safety injection tank when an accident of loss of coolant occurs. The safety injection line has an orifice and a check valve thereon, and the pressure balance line has an orifice and an isolation valve thereon. The water in the safety injection tank flows into the reactor stably for several hours.
For another example, chinese patent application 201510272061.8 discloses a safety injection system, which comprises a medium-pressure safety injection subsystem, a low-pressure safety injection subsystem and a safety injection tank injection subsystem, wherein one end of the medium-pressure safety injection subsystem and one end of the low-pressure safety injection subsystem take water through a refueling water tank arranged in a containment vessel, and the other end of the medium-pressure safety injection subsystem and the low-pressure safety injection subsystem supply water to a primary circuit cold section and a primary circuit hot section; the medium-pressure safety injection subsystem and the low-pressure safety injection subsystem respectively comprise an A row and a B row; the A line of the medium-pressure safety injection subsystem and the A line of the low-pressure safety injection subsystem respectively comprise an A1 medium-pressure safety injection pump, an A2 low-pressure safety injection pump and a connecting pipeline which are arranged outside the containment; the B line of the medium-pressure safety injection subsystem and the B line of the low-pressure safety injection subsystem respectively comprise a B1 medium-pressure safety injection pump and a B2 low-pressure safety injection pump which are arranged outside the containment and a connecting pipeline.
The waste heat removal system functions primarily to remove heat from the core and the reactor coolant system during shutdown of the nuclear power plant after initial cooling and depressurization by the steam generator.
There are also some reports in the prior art regarding residual heat removal systems.
For example, chinese patent application 201710213255.X discloses a waste heat removal system for a nuclear reactor, which includes a primary circuit non-safety level waste heat removal subsystem, a primary circuit safety level waste heat removal subsystem and a containing body passive cooling subsystem, the three subsystems are connected in parallel and operate according to the safety accident level, a normal shutdown without an accident depends on the primary circuit non-safety level waste heat removal subsystem to derive waste heat, when an accident occurs to a secondary circuit of the reactor or the whole plant is powered off, the non-safety level waste heat removal system cannot be used, the primary circuit safety level waste heat removal subsystem is discharged and put into use, and when the accident is serious, the containing body passive cooling subsystem is triggered to operate.
For another example, chinese patent application 201811343185.0 discloses a waste heat removal system, which includes a reactor pressure vessel, a reactor coolant pump, and a waste heat removal cooler, wherein hot water in the reactor pressure vessel flows into the reactor coolant pump, is cooled, and then flows back to the reactor pressure vessel, a cold-section pipe of the reactor coolant pump is simultaneously connected to an inflow pipe of the waste heat removal cooler, and an outflow pipe of the waste heat removal cooler is connected to a hot-section pipe of the reactor pressure vessel.
Disclosure of Invention
The invention aims to provide a safety injection and waste heat removal system for a nuclear power plant, which can ensure the safety of the nuclear power plant when a reactor has an accident, greatly improve the safety of the nuclear power plant, and simultaneously consider the functions of the waste heat removal system when the reactor is started and stopped, thereby greatly saving the investment of the nuclear power plant and improving the economy of the nuclear power plant.
To achieve the purpose, in a basic embodiment, the invention provides a nuclear power plant safety injection and residual heat removal system, which comprises a high-pressure safety injection tank injection circuit, a safety injection pump injection circuit (residual heat removal circuit), a reactor pressure vessel,
the high-pressure safety injection box injection loop comprises a high-pressure safety injection box inlet pipeline, a high-pressure safety injection box (a loop is subjected to small-flow water supplement in case of small-break accident) and a high-pressure safety injection box outlet pipeline which are sequentially connected, wherein the top of the high-pressure safety injection box is connected with a reactor coolant system cold pipe section through the high-pressure safety injection box inlet pipeline, and the bottom of the high-pressure safety injection box is connected with a reactor pressure container or a reactor coolant system cold pipe section through the high-pressure safety injection box outlet pipeline;
the safety injection box injection loop comprises safety injection boxes (for performing large-flow water supplement on the loop in case of large and medium break accidents) and a safety injection box outlet pipeline which are connected with each other, wherein the bottom of each safety injection box is connected with the reactor pressure vessel or the cold pipe section of the reactor coolant system through the safety injection box outlet pipeline;
the safety injection pump injection loop (waste heat discharge loop) comprises a safety injection pump inlet pipeline, a safety injection pump (providing long-term cooling for a reactor), a safety injection pump outlet pipeline, a built-in refueling water tank and a heat exchanger (used for leading out reactor core heat when the system executes safety injection and waste heat discharge functions), the safety injection pump inlet pipeline is connected with the built-in refueling water tank and a reactor coolant system heat pipe section, and the safety injection pump outlet pipeline is connected with the heat exchanger after being cooled and then is connected with a reactor pressure container or is connected with the reactor coolant system heat pipe section and a reactor cold pipe section.
In a preferred embodiment, the invention provides a nuclear power plant safety injection and residual heat removal system, wherein the high-pressure safety injection tank injection circuit, the safety injection tank injection circuit and the safety injection pump injection circuit (residual heat removal circuit) are respectively in one or more rows.
In a more preferred embodiment, the invention provides a nuclear power plant safety injection and residual heat removal system, wherein each row of the high-pressure safety injection tank injection circuit, the safety injection tank injection circuit and the safety injection pump injection circuit (residual heat removal circuit) are powered by independent power supplies and are provided with independent emergency diesel engines.
In a preferred embodiment, the invention provides a safety injection and residual heat removal system for a nuclear power plant, wherein the top of the interior of a safety injection box is filled with high-pressure nitrogen.
In a preferred embodiment, the invention provides a nuclear power plant safety injection and residual heat removal system, wherein the high-pressure safety injection tank outlet pipeline, the safety injection tank outlet pipeline and the safety injection pump outlet pipeline share a part of pipelines in pairs or in three parts.
In a more preferred embodiment, the present invention provides a nuclear power plant safety injection and residual heat removal system, wherein the high-pressure safety injection tank injection circuit further comprises:
the non-shared part of the outlet pipeline of the high-pressure safety injection tank is provided with a first normally closed electric valve, a second normally closed electric valve and a first check valve in parallel;
and a normally open third electric valve is arranged on the inlet pipeline of the high-pressure safety injection tank.
In a more preferred embodiment, the present invention provides a nuclear power plant safety injection and residual heat removal system, wherein the safety injection tank injection circuit further comprises:
and a normally-open fourth electric valve and a second check valve are arranged in series on the non-shared part of the outlet pipeline of the safety injection tank.
In a more preferred embodiment, the present invention provides a nuclear power plant safety injection and residual heat removal system, wherein the injection pump injection circuit further comprises:
a fifth normally closed electric valve and a sixth normally open electric valve are arranged on the inlet pipeline of the safety injection pump;
and the non-shared part of the safety injection pump outlet pipeline is provided with a normally open seventh electric valve, a fourth check valve and a fifth check valve in series.
In a more preferred embodiment, the present invention provides a nuclear power plant safety injection and residual heat removal system, wherein the system further comprises a third check valve disposed on a portion of the high pressure safety injection tank outlet line common to the safety injection tank outlet line.
The system has the advantages that the system for safely injecting and discharging the residual heat of the nuclear power plant adopts the passive high-pressure safety injection box, the safety injection box injection loop and the active safety injection pump injection loop, can ensure the safety of the nuclear power plant when a reactor has an accident, greatly improves the safety of the nuclear power plant, and simultaneously considers the function of the residual heat discharge system when the reactor is started and stopped, thereby greatly saving the investment of the nuclear power plant and improving the economy of the nuclear power plant.
Drawings
Fig. 1 is a block diagram of an exemplary nuclear power plant safety injection and residual heat removal system of the present invention.
Detailed Description
The following further describes embodiments of the present invention with reference to the accompanying drawings.
An exemplary system for safely injecting and discharging waste heat from a nuclear power plant according to the present invention is shown in fig. 1, and includes a high-pressure safety injection tank injection circuit, a safety injection pump injection circuit (waste heat discharge circuit), a reactor pressure vessel 5, a steam generator 6, and a main pump 7.
When the nuclear power plant is in operation, high-temperature coolant in the reactor pressure vessel 5 enters the steam generator 6 through the main loop heat pipe section to be cooled, and then returns to the reactor pressure vessel 5 through the main pump 7 through the transition section after being cooled.
The high-pressure safety injection box injection loop comprises a high-pressure safety injection box inlet pipeline 11, a high-pressure safety injection box 12 (a loop is subjected to small-flow water supplement during small-break accidents) and a high-pressure safety injection box outlet pipeline 13 which are sequentially connected, wherein the top of the high-pressure safety injection box 12 is connected with a reactor coolant system cold pipe section through the high-pressure safety injection box inlet pipeline 11, and the bottom of the high-pressure safety injection box 12 is connected with a reactor pressure container 5 or a reactor coolant system cold pipe section through the high-pressure safety injection box outlet pipeline 13.
The safety injection box injection loop comprises a safety injection box 21 (for performing large-flow water supplement on one loop in case of large and medium breach accidents) and a safety injection box outlet pipeline 22 which are connected with each other, wherein the top inside the safety injection box 21 is filled with high-pressure nitrogen, and the bottom of the safety injection box 21 is connected with the reactor pressure vessel 5 or a cold pipe section of a reactor coolant system through the safety injection box outlet pipeline 22.
The safety injection pump injection loop (waste heat discharge loop) comprises a safety injection pump inlet pipeline 31, a safety injection pump 32 (providing long-term cooling for a reactor), a safety injection pump outlet pipeline 33, a built-in refueling water tank 34 and a heat exchanger 35 (used for leading out reactor core heat when the system performs safety injection and waste heat discharge functions), the safety injection pump inlet pipeline 31 is connected with the built-in refueling water tank 34 and a reactor coolant system heat pipe section, and the safety injection pump outlet pipeline 33 is connected with the reactor pressure container 5 or the reactor coolant system heat pipe section and a reactor coolant system cold pipe section after being cooled by the heat exchanger 35.
The injection loop of the high-pressure safety injection tank, the injection loop of the safety injection tank and the injection loop (residual heat removal loop) of the safety injection pump are respectively 1-4 rows. Each row of high-pressure safety injection tank injection loop, safety injection tank injection loop and safety injection pump injection loop (waste heat discharge loop) are powered by independent power supplies and are provided with independent emergency diesel engines.
The high-pressure safety injection tank outlet line 13 and the safety injection tank outlet line 22 share a part of the lines, and a third check valve 18 (which prevents the reverse flow of the reactor coolant into the high-pressure safety injection tank 12 and the safety injection tank 21 and ensures the tightness of the reactor coolant system during the normal operation of the nuclear power plant) is provided on the shared part of the lines.
A first electric valve 14 and a second electric valve 15 which are normally closed (ensuring the isolation of the high-pressure safety injection tank 12 from the reactor coolant system) and a first check valve 16 (preventing the reverse flow of the reactor coolant into the high-pressure safety injection tank 12 and ensuring the tightness of the reactor coolant system during the normal operation of the nuclear power plant) are provided in parallel on the non-common portion of the high-pressure safety injection tank outlet line 13. A normally open third electric valve 17 is arranged on the inlet pipeline 11 of the high-pressure safety injection tank (the top of the high-pressure safety injection tank 12 is communicated with the reactor coolant system).
A normally open fourth electric valve 23 (which can timely inject the liquid in the safety injection tank 21 into the reactor coolant system when the reactor coolant system has an accident) and a second check valve 24 (which can prevent the reactor coolant from flowing back into the safety injection tank 21 when the reactor is in normal operation and can ensure the tightness of the reactor coolant system during the normal operation of the nuclear power plant) are arranged in series on the non-shared part of the outlet pipeline 22 of the safety injection tank.
A normally closed fifth electric valve 36 (which is opened when the system executes a normal waste heat discharge function, and a sixth electric valve 37 between the safety injection pump 32 and the built-in refueling water tank 34 is closed at the same time) and a normally open sixth electric valve 37 (which ensures that the safety injection pump 32 can directly take water from the built-in refueling water tank 34 after an accident and realizes reactor core cooling) are arranged on the inlet pipeline 31 of the safety injection pump, wherein the reactor coolant is pumped out from a reactor cooling and system heat pipe section and is injected into the reactor pressure vessel 5 or a cold pipe section after being cooled by the heat exchanger 35. A seventh, normally open electric valve 38 (for isolated servicing of system equipment), a fourth check valve 39 and a fifth check valve 30 (check valves in series are used to ensure the tightness of the reactor coolant system during normal operation of the nuclear power plant) are arranged in series on the safety injection pump outlet line 33.
The main advantages of the above system are: when the accident condition such as the break of the main loop (the hot section, the transition section, the cold section and the like of the main loop) occurs, the water supplement of the main loop can be realized through the high-pressure safety injection box when the pressure of the main loop is higher, the water is injected into the main loop through the safety injection box when the pressure is reduced to the injection pressure of the safety injection box, and the water in the water tank is injected into the main loop when the material is replaced in the containment through the safety injection pump when the pressure is reduced to the injection pressure head of the safety injection pump, so that the safety of a reactor is ensured; meanwhile, the heat of the reactor core is led out of the containment through a heat exchanger at the outlet of the safety injection pump, so that the pressure and the temperature in the containment after an accident are controlled; when the reactor is normally shut down, the heat of the reactor core can be led out through the safety injection pump and the heat exchanger at the outlet of the safety injection pump, so that the function of normally discharging waste heat is realized.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations. The above-described embodiments are merely illustrative of the present invention, and the present invention may be embodied in other specific forms or other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.
Claims (6)
1. The utility model provides a nuclear power plant safety injection and waste heat removal system which characterized in that: the system comprises a high-pressure safety injection tank injection loop, a safety injection pump injection loop and a reactor pressure vessel,
the high-pressure safety injection box injection loop comprises a high-pressure safety injection box inlet pipeline, a high-pressure safety injection box and a high-pressure safety injection box outlet pipeline which are sequentially connected, the top of the high-pressure safety injection box is connected with a reactor coolant system cold pipe section through the high-pressure safety injection box inlet pipeline, and the bottom of the high-pressure safety injection box is connected with a reactor pressure container or a reactor coolant system cold pipe section through the high-pressure safety injection box outlet pipeline;
the safety injection box injection loop comprises a safety injection box and a safety injection box outlet pipeline which are connected with each other, and the bottom of the safety injection box is connected with the reactor pressure vessel or the cold pipe section of the reactor coolant system through the safety injection box outlet pipeline;
the safety injection pump injection loop comprises a safety injection pump inlet pipeline, a safety injection pump outlet pipeline, a built-in refueling water tank and a heat exchanger which are sequentially connected, the safety injection pump inlet pipeline is connected with the built-in refueling water tank and a reactor coolant system heat pipe section, the safety injection pump outlet pipeline is connected with the reactor pressure container or connected with the reactor coolant system heat pipe section and a cold pipe section after being cooled by the heat exchanger,
the high-pressure safety injection tank injection loop, the safety injection tank injection loop and the safety injection pump injection loop are respectively in one row or multiple rows;
the high-pressure safety injection tank injection loop, the safety injection tank injection loop and the safety injection pump injection loop of each row are powered by independent power supplies, and are provided with independent emergency diesel engines;
the high-pressure safety injection tank outlet pipeline, the safety injection tank outlet pipeline and the safety injection pump outlet pipeline share a part of pipelines in pairs or in pairs.
2. The system of claim 1, wherein: the top of the interior of the safety injection box is filled with high-pressure nitrogen.
3. The system of claim 1, wherein said high pressure safety injection tank injection circuit further comprises:
the normally closed first electric valve, the normally closed second electric valve and the first check valve are arranged on the non-shared part of the outlet pipeline of the high-pressure safety injection tank in parallel;
and a normally open third electric valve is arranged on the inlet pipeline of the high-pressure safety injection tank.
4. The system of claim 1, wherein said safety tank injection circuit further comprises:
and a normally-open fourth electric valve and a second check valve are arranged in series on the non-shared part of the outlet pipeline of the safety injection tank.
5. The system of claim 1, wherein said safety pump injection circuit further comprises:
a fifth normally closed electric valve and a sixth normally open electric valve are arranged on the inlet pipeline of the safety injection pump;
and the non-shared part of the safety injection pump outlet pipeline is provided with a normally open seventh electric valve, a fourth check valve and a fifth check valve in series.
6. The system of claim 1, wherein: the system also includes a third check valve disposed on a common portion of the high pressure safety tank outlet line and the safety tank outlet line.
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Families Citing this family (5)
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| CN110752046B (en) * | 2019-10-12 | 2022-01-11 | 中国核电工程有限公司 | Safety device, nuclear power plant system and safe operation method of nuclear power plant |
| CN111540486A (en) * | 2020-04-16 | 2020-08-14 | 中国核动力研究设计院 | Small pressurized water reactor and long-term passive heat discharge system of containment |
| CN111540483B (en) * | 2020-05-15 | 2022-02-11 | 中国核动力研究设计院 | Method for coping with small-sized crevasse loss of coolant accident in pressurized water reactor nuclear power plant |
| CN112582083A (en) * | 2020-12-09 | 2021-03-30 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Heat conduction system and heat conduction method suitable for nuclear reactor containment system for ship |
| CN113808764B (en) * | 2021-08-03 | 2023-09-19 | 中国核电工程有限公司 | Method and system for guiding out residual heat of reactor core in containment |
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