CN107293338B - Nuclear reactor safety system - Google Patents
Nuclear reactor safety system Download PDFInfo
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- CN107293338B CN107293338B CN201610862926.0A CN201610862926A CN107293338B CN 107293338 B CN107293338 B CN 107293338B CN 201610862926 A CN201610862926 A CN 201610862926A CN 107293338 B CN107293338 B CN 107293338B
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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
- G21D—NUCLEAR POWER PLANT
- G21D9/00—Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
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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
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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 discloses a nuclear reactor safety system, comprising: the reactor comprises a water tank, a reactor container, a reactor core, a first heat exchanger, an passive waste heat exchanger and a first isolation valve, wherein the reactor container is arranged below the liquid level in the water tank, the reactor core is arranged in the reactor container, the first heat exchanger is connected with a container inlet and a container outlet of the reactor container to form a closed first loop, the first heat exchanger is connected with a heat supply network, water in the reactor container exchanges heat with water in the heat supply network through the first heat exchanger, the passive waste heat exchanger is arranged below the liquid level in the water tank, the passive waste heat exchanger is connected with the first loop and used for leading heat in the first loop out to the water tank when an accident occurs to the reactor, and a first isolation valve which is closed during normal operation of the reactor and opened during the accident occurs to the reactor is arranged on a pipeline between the passive waste heat exchanger and the first loop. The nuclear reactor safety system provided by the embodiment of the invention has the advantages of simple structure and high safety.
Description
Technical Field
The present invention relates to the field of nuclear reactor technology, and more particularly, to a nuclear reactor safety system.
Background
At present, the heating mode in China mainly uses coal as a main source, coal resources are non-renewable energy sources, the resources are scarce, the combustion process can cause serious environmental pollution, with the development of nuclear heating reactor technology, the consumption of traditional fossil energy sources can be reduced by utilizing nuclear energy for heating, the environment is better protected, the civil field of nuclear energy can be widened, and the heating application is increased on the basis of original power generation application. The nuclear heating reactor in the related art is usually a shell type reactor, systems such as emergency safety water injection and spraying facilities and the like are required to be arranged, a process system and a safety system are complex, investment cost is high, and when the pool type heating reactor has accidents, different equipment is required to be adopted for treatment, so that the safety performance is poor.
Disclosure of Invention
The present invention aims to solve at least to some extent one of the above technical problems.
Therefore, the invention provides a nuclear reactor safety system which has simple structure, low cost and high safety.
A nuclear reactor safety system according to an embodiment of the present invention includes: the reactor comprises a water tank, a reactor vessel, a reactor core, a first heat exchanger, a passive waste heat exchanger and a first isolation valve, wherein the reactor vessel is arranged in the water tank and is positioned below the liquid level in the water tank, the reactor vessel is provided with a vessel inlet and a vessel outlet, the reactor core is positioned in the reactor vessel, the first heat exchanger is positioned outside the reactor vessel, the first heat exchanger is connected with the vessel inlet and the vessel outlet of the reactor vessel to form a closed first loop, the first heat exchanger is suitable for being connected with a heat supply network, water in the reactor vessel is in heat exchange with water in the heat supply network through the first heat exchanger, the passive waste heat exchanger is arranged in the water tank and is positioned below the liquid level in the water tank, the passive waste heat exchanger is connected with the first loop and is used for leading heat in the first loop out to the water tank when an accident occurs, the first isolation valve is arranged between the passive waste heat exchanger and a first loop and is closed when the reactor is in normal operation.
According to the nuclear reactor safety system provided by the embodiment of the invention, the reactor vessel is arranged in the water tank, the pipeline is used for communicating the first heat exchanger, heat generated by the core reactor in the inner cavity of the reactor vessel is used for supplying heat to the heat supply network, the passive waste heat exchanger communicated with the reactor vessel is arranged in the water tank, the first isolation valve is used for controlling the conduction of the pipeline between the passive waste heat exchanger and the first loop, normal operation heat supply of the pool type heat supply reactor can be ensured, the safety performance of the pool type heat supply reactor can be improved, when an accident occurs in the pool type heat supply reactor, the passive waste heat exchanger is used for transmitting the heat in the reactor vessel to the water tank, the water in the water tank is used for absorbing the heat of the pool type heat supply reactor, the reactor accident is prevented from inducing larger safety accident, the nuclear reactor safety system is simple in structure and low in cost, the core is controlled in the water tank, the nuclear leakage can be prevented, and the safety performance of the hazard degree is high.
In addition, the nuclear reactor safety system according to the embodiment of the present invention may further have the following additional technical features:
according to one embodiment of the invention, the nuclear reactor safety system further comprises: the heat exchanger comprises an internal heat exchanger and an external heat exchanger, wherein the internal heat exchanger is arranged in the water tank and below the liquid level in the water tank, and the external heat exchanger is arranged outside the water tank and used for guiding out heat in the water tank.
According to one embodiment of the invention, the nuclear reactor safety system further comprises a loop regulator, the loop regulator is arranged outside the water tank, the loop regulator is connected with the first loop to regulate the pressure in the first loop, and the loop regulator sends out a signal for controlling the opening of the first isolation valve when the reactor is in a non-break accident and the pressure in the loop regulator is higher than a preset value.
According to one embodiment of the invention, the nuclear reactor safety system further comprises a containment vessel, the pool of water is disposed within the containment vessel, and the external heat exchanger is disposed outside the containment vessel.
According to one embodiment of the invention, the nuclear reactor safety system further comprises a water reservoir in communication with the pool for replenishing water within the pool.
According to one embodiment of the invention, the pressure in the circuit between the first heat exchanger and the heating network is greater than the pressure in the first circuit.
According to one embodiment of the invention, the pressure in the first circuit is a micro-pressure of 1.5-20 normal atmospheres.
According to one embodiment of the invention, the pressure in the first circuit is 5-12 normal atmospheres.
According to one embodiment of the invention, the pressure in the first circuit is 6-9 normal atmospheres.
According to one embodiment of the invention, the nuclear reactor safety system further comprises a safety water replenishment pipe provided in the tank and a safety water replenishment valve provided on the safety water replenishment pipe, the safety water replenishment pipe being in communication with the reactor vessel at one end and with the tank at the other end, the safety water replenishment valve being opened for water injection into the reactor vessel when an accident occurs in the reactor and the pressure in the reactor vessel is lower than the pressure in the tank.
Additional aspects and advantages of the invention will be set forth in part in the description which follows, and in part will be obvious from the description, or may be learned by practice of the invention.
Drawings
The foregoing and/or additional aspects and advantages of the invention will become apparent and may be better understood from the following description of embodiments taken in conjunction with the accompanying drawings in which:
fig. 1 is a schematic structural view of a nuclear reactor safety system according to an embodiment of the present invention.
Reference numerals:
100: nuclear reactor safety system
10: a pool; 11: a containment vessel;
20: a reactor vessel; 21: a container inlet; 22: a container outlet; 23: a safety water supplementing pipe; 24: safety patch
A water valve;
30: a first heat exchanger; 31: a first inlet; 32: a first outlet; 33: a voltage stabilizer; 34: a pressure relief tank; 35:
a pressure relief valve; 36: a safety valve; 37: a compartment;
40: a passive waste heat exchanger; 41: a second inlet; 42: a second outlet;
50: a first isolation valve; 51: a second isolation valve;
60: a heat exchanger is arranged in the heat exchanger; 61: an external heat exchanger; 70: a cold pipe; 80: a heat pipe; 90: a non-return valve.
Detailed Description
Embodiments of the present invention are described in detail below, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to like or similar elements or elements having like or similar functions throughout. The embodiments described below by referring to the drawings are illustrative and intended to explain the present invention and should not be construed as limiting the invention.
A nuclear reactor safety system 100 in accordance with an embodiment of the present invention is described in detail below with reference to fig. 1.
As shown in fig. 1, a nuclear reactor safety system 100 according to an embodiment of the present invention includes: a pool 10, a reactor vessel 20, a core (not shown), a first heat exchanger 30, a passive waste heat exchanger 40, and a first isolation valve 50.
Specifically, the reactor vessel 20 is disposed in the water tank 10 below the water level in the water tank 10, the reactor vessel 20 has a vessel inlet 21 and a vessel outlet 22, the reactor core is disposed in the reactor vessel 20, the first heat exchanger 30 is disposed outside the reactor vessel 20, the first heat exchanger 30 is connected to the vessel inlet 21 and the vessel outlet 22 of the reactor vessel 20 to form a closed first circuit, the first heat exchanger 30 is connected to a heating network (not shown), water in the reactor vessel 20 exchanges heat with water in the heating network through the first heat exchanger 30, the passive waste heat exchanger 40 is disposed in the water tank 10 below the water level in the water tank 10, the passive waste heat exchanger 40 is connected to the first circuit for conducting heat in the first circuit into the water tank 10 in the event of a reactor accident, the first isolation valve 50 is disposed on a pipe between the passive waste heat exchanger 40 and the first circuit, and the first isolation valve 50 is closed in normal operation of the reactor and opened in the event of a reactor accident.
In other words, the nuclear reactor safety system 100 mainly comprises a pool 10, a reactor vessel 20, a reactor core, a first heat exchanger 30, a passive waste heat exchanger 40 and a first isolation valve 50, wherein the reactor vessel 20 is arranged under the water surface of the pool 10, a vessel inlet 21 and a vessel outlet 22 are arranged on one side of the reactor vessel 20, the vessel inlet 21 and the vessel outlet 22 are communicated with the inner cavity of the reactor vessel 20, the reactor vessel 20 is internally provided with the reactor core, the vessel inlet 21 and the vessel outlet 22 of the reactor vessel 20 are respectively communicated with a first inlet 31 and a first outlet 32 of the first heat exchanger 30 through a heat pipe 80 and a cold pipe 70, the first heat exchanger 30 is communicated with the reactor vessel 20 through the vessel inlet 21 and the vessel outlet 22 to form a first loop (not shown), a second isolation valve 51 is arranged on the cold pipe 70, a check valve 90 is arranged on the heat pipe 80, and a cooling liquid is arranged in the heat pipe 70 and the heat pipe 80, and the cooling liquid flows between the first heat exchanger 30 and the reactor vessel 20 to perform heat exchange.
The water tank 10 is further internally provided with a passive waste heat exchanger 40, the passive waste heat exchanger 40 is located below the water surface in the water tank 10, one end of the passive waste heat exchanger 40 is provided with a second inlet 41, the other end of the passive waste heat exchanger 40 is provided with a second outlet 42, the second inlet 41 and the second outlet 42 are respectively communicated with a cold pipe 70 and a heat pipe 80 in the first loop, the passive waste heat exchanger 40 exchanges heat with the first loop by using cooling liquid, a first isolation valve 50 is arranged on a pipeline between the passive waste heat exchanger 40 and the first loop, and the first isolation valve 50 can control the opening and closing of the pipeline between the passive waste heat exchanger 40 and the first loop, and further control the opening and closing of the heat exchange by controlling the flow of the cooling liquid between the passive waste heat exchanger 40 and the first loop.
When an accident occurs in the pool type heating reactor, the first isolation valve 50 is opened, a pipeline between the passive waste heat exchanger 40 and the first loop is conducted, and by utilizing the connection function of the first loop, two ports of the passive waste heat exchanger 40 are respectively communicated with the container inlet 21 and the container outlet 22 of the reactor container 20 and two ports of the first heat exchanger 30, and heat exchange among the passive waste heat exchanger 40, the first heat exchanger 30 and the reactor container 20 is realized through circulation of cooling liquid in the communication pipeline.
Thus, according to the nuclear reactor safety system 100 of the embodiment of the present invention, the reactor vessel 20 is disposed in the pool 10, the first heat exchanger 30 is connected by the pipe, the heat generated by the core reaction in the inner cavity of the reactor vessel 20 is supplied to the heating grid, the passive waste heat exchanger 40 connected to the reactor vessel 20 is disposed in the pool 10, the first isolation valve 50 is used to control the conduction of the pipe between the passive waste heat exchanger 40 and the first circuit, so that the normal operation and heat supply of the pool type heating reactor can be ensured, the safety performance of the pool type heating reactor can be improved, the heat in the reactor vessel 20 is transferred to the pool 10 by the passive waste heat exchanger 40 when the pool type heating reactor has an accident, the heat emitted by the pool type heating reactor is absorbed by the water in the pool 10, the pool type heating reactor accident is prevented from inducing a larger safety accident, the nuclear reactor safety system 100 is simple in structure and low in cost, the core leakage can be prevented, and the safety performance of the accident can be reduced.
Further, the nuclear reactor safety system 100 further includes a containment vessel 11, the pool 10 is provided within the containment vessel 11, an external heat exchanger 61 is provided outside the containment vessel 11, and the containment vessel 11 is installed at the bottom, side and upper portions of the pool 10 to accommodate and cover the pool 10. Specifically, as shown in fig. 1, a safety shell 11 is arranged on the periphery of the water tank 10, the safety shell 11 can seal and cover the upper part, the side part and the bottom of the water tank 10, an accommodating cavity is arranged in the inner cavity of the water tank 10, water is arranged in the accommodating cavity to form the water tank 10, and a reactor vessel 20 and a passive waste heat exchanger 40 are arranged in the water tank 10, so that the safety of a reactor system is ensured.
Through setting up containment 11 in pond 10 periphery, not only can inject and hold the chamber and be used for holding pond 10 and pond formula heat supply reactor, can also form the protective housing and wrap up pond formula heat supply reactor, on the one hand can reduce the interference influence of external environment to pond formula heat supply reactor, on the other hand can prevent that the pond formula heat supply reactor from taking place to leak or injuring staff around when taking place the accident, moreover, containment 11 simple structure realizes easily, and the practicality is strong, improves the security of pond formula heat supply reactor system.
Preferably, the nuclear reactor safety system 100 further includes an internal heat exchanger 60 and an external heat exchanger 61, the internal heat exchanger 60 is disposed in the pool 10 and below the liquid level in the pool 10, the external heat exchanger 61 is disposed outside the pool 10 for guiding out heat in the pool 10, as shown in fig. 1, the internal heat exchanger 60 is disposed in the pool 10 and not below the water level, the internal heat exchanger 60 is ensured to be in full contact with water, the internal heat exchanger 60 is communicated with the external heat exchanger 61 through a pipeline, and a cooling liquid is disposed in the internal heat exchanger 60 and the external heat exchanger 61 and in the pipeline therebetween, and flows between the internal heat exchanger 60 and the external heat exchanger 61 to realize heat exchange.
The internal heat exchanger 60 and the external heat exchanger 61 are respectively arranged inside and outside the water tank 10 and are communicated through a pipeline, so that heat in the water tank 10 can be transferred to the outside of the water tank 10 in time, water in the water tank 10 is guaranteed to be in a lower temperature state, the working efficiency of the passive waste heat exchanger 40 can be increased, the heat exchange efficiency of the passive waste heat exchanger 40 and water flow in the water tank 10 is improved, and further the heat diffusion efficiency and speed in the reactor vessel 20 are increased, therefore, the internal heat exchanger 60 and the external heat exchanger 61 work in a coordinated manner with the passive waste heat exchanger 40 to form a series of stable heat exchange systems, heat accumulation during accidents of the pool type heat supply reactor is reduced, the accident hazard is reduced, and the use safety and the control of the pool type heat supply reactor are improved.
Advantageously, the nuclear reactor safety system 100 further comprises a loop regulator 33, the loop regulator 33 is disposed outside the pool 10, one end of the loop regulator 33 is connected to the heat pipe 80, the other end is connected to the pressure relief tank 34, a pressure relief valve 35 is disposed between the pressure relief tank 34 and the loop regulator 33, the pressure relief valve 35 and the loop regulator 33 are in communication with pool water through a pipeline, a safety valve 36 is disposed on the connecting pipeline, and the loop regulator 33 and the first heat exchanger 30 are isolated from the reactor by a partition 37.
A circuit stabilizer 33 is connected to the first circuit to regulate the pressure in the first circuit, and the circuit stabilizer 33 signals to control the opening of the first isolation valve 50 when a non-break accident occurs in the reactor and the pressure in the circuit stabilizer 33 is higher than a predetermined value.
Specifically, a circuit stabilizer 33 is connected to the pipeline between the reactor vessel 20 and the first heat exchanger 30 in the first circuit, and the circuit stabilizer 33 is connected to the first circuit through the pipeline, so as to regulate the pressure in the first circuit, for example, when a non-break accident occurs in the pool type heating reactor and the pressure in the circuit stabilizer 33 is higher than a predetermined value, the circuit stabilizer 33 sends a signal to control the opening and closing of the first isolation valve 50.
When a non-break accident occurs in the reactor, the nuclear reactor safety system 100 is in an accident initial stage, the cooling fluid pressure and the temperature in the first loop rise, the loop voltage stabilizer 33 sends out an opening signal of the first isolation valve 50, the first isolation valve 50 opens a pipeline between the passive waste heat exchanger 40 and the first loop, heat exchange between the passive waste heat exchanger 40 and the reactor vessel 20 is realized, heat in the reactor vessel 20 is transferred to water, the heat is further transferred to the outside of the containment 11 through the internal heat exchanger 60 and the external heat exchanger 61, on one hand, the heat transferred from the pool-type heating reactor to the first heat exchanger 30 can be reduced, on the other hand, the temperature and the pressure in the reactor vessel 20 are reduced, the reactor core is prevented from being damaged to a greater extent, break of the first loop is prevented under the action of high temperature and high pressure, the safety performance of nuclear energy utilization is improved, the opening and closing of the first isolation valve 50 are automatically controlled by the loop voltage stabilizer 33, no self-operation of operators is needed, and the damage to operators is reduced.
Optionally, the nuclear reactor safety system 100 further comprises a reservoir (not shown) in communication with the basin 10 for replenishing water into the basin 10, that is, the nuclear reactor safety system 100 further enhances the safety of the system by providing a reservoir, and when the water level in the basin 10 drops to a certain level, a valve on a pipe connecting the reservoir and the basin 10 is opened to replenish water into the basin 10.
The water in the water tank 10 is ensured not to be lower than a certain height by utilizing the water storage tank to supplement water for the water tank 10, for example, when the water quantity in the water tank 10 is lower than the certain height, the water storage tank is used for supplementing water for the water tank 10, when the water level in the water tank 10 reaches a certain height, the water storage tank stops supplementing water for the water tank 10, the safety of the pool type heat supply reactor is prevented from being influenced by too little water quantity in the water tank 10, and when the pool type heat supply reactor is ensured to fail, the water in the water tank 10 is enough for the pool type heat supply reactor to dissipate heat.
Preferably, the pressure in the circuit between the first heat exchanger 30 and the heating network is greater than the pressure in the first circuit, that is to say the pressure in the first circuit is lower, i.e. the pressure of the cooling liquid in the pipe cavity between the inlet 21 of the vessel and the outlet 22 of the vessel 20 is lower, the communication pipe between the first heat exchanger 30 and the second heat exchanger (not shown) forms a second circuit, the pressure of the cooling liquid in the second circuit is higher, and a third circuit is formed between the second heat exchanger and the heating network (not shown).
The pressure of the first loop is low, and when the main loop of the reactor is damaged, particularly when the first heat exchanger 30 is damaged, the pressure of the cooling liquid between the first heat exchanger 30 and the heating network is high, so that the cooling liquid in the first loop cannot leak, the reactor core is prevented from being damaged due to the loss or evaporation of the cooling liquid in the reactor container 20, and the low-temperature micro-pressure characteristic enables the reactor to have the condition of reducing the safety level of equipment.
Alternatively, the pressure in the first circuit is a micropressure of 1.5-20 normal atmospheres. Advantageously, the pressure in the first circuit is a micro-pressure of 5-12 normal atmospheres. Preferably, the pressure in the first circuit is 6-9 atmospheres gauge.
The operation parameters of the heating pile are determined by balancing and solidifying the design scheme and the technical requirements of a user side (a heating network). Too low an operating pressure (less than 1.5 atmospheres) can lead to too low a reactor outlet problem (only up to around 100 ℃), which is difficult to accommodate for the needs of the municipal heating network (large heating network return water temperature requirement 110 ℃). Although the excessive pressure (for example, more than 20 atmospheres) can greatly increase the outlet temperature of the reactor core (for example, the pressurized water reactor can reach about 150 atmospheres and the outlet temperature can reach more than 310 ℃), the high pressure can cause problems of greatly increased cost, complicated system, greatly reduced safety of the reactor and the like. According to the optimal design, the optimal pressure section of the micro-pressure heat supply pile is between 5 and 12 standard atmospheres, and the operating pressure range can realize the requirements of a large-scale heat supply network (the heat supply temperature is more than 120 ℃) and part of industrial heat supply on the premise of ensuring the inherent safety of the reactor. If the design scheme of the micropressure heat supply pile adopts 6 atmospheres (within the range of 6-9 standard atmospheres), the outlet temperature of the system can reach 120 ℃, the technical requirements of a large-scale heat supply network are completely met, meanwhile, the economy and the safety are well considered, and the system is an optimized scheme special for resident heat supply.
It should be noted that the micro pressure is the pressure of the cooling liquid in the first circuit, or may be the pressure of the vessel outlet 22, and the pressure of the vessel outlet 22 is slightly smaller than the pressure at the core due to a certain amount of pressure loss generated between the core and the vessel outlet 22.
The specific parameters of the cooling fluid pressure in the first loop can be adaptively adjusted according to the actual design requirements of the cooling fluid pressure in the second loop, the pool water pressure in the pool 10 and the like, so that the heat supply parameters of the pool heat supply reactor can be improved under normal operation working conditions, and when an accident occurs, the reactor core can be ensured not to be exposed due to the great loss of cooling water, so that the pool heat supply reactor has the condition of reducing the safety level, and the equipment cost is reduced.
The nuclear reactor safety system 100 further includes a safety water replenishment pipe 23 and a safety water replenishment valve 24, the safety water replenishment pipe 23 is provided in the pool 10, the safety water replenishment valve 24 is provided on the safety water replenishment pipe 23, one end of the safety water replenishment pipe 23 is communicated with the reactor vessel 20 and the other end is communicated with the pool 10, and the safety water replenishment valve 24 is opened when an accident occurs in the reactor and the pressure in the reactor vessel 20 is lower than the pressure in the pool 10 so that water in the pool 10 is injected into the reactor vessel 20.
Referring to fig. 1, a safety water supplementing pipe 23 is arranged at the bottom of the reactor vessel 20, one end of the safety water supplementing pipe 23 is connected with the bottom wall of the reactor vessel 20 and is communicated with the inner cavity of the reactor vessel 20, the other end of the safety water supplementing pipe 23 is positioned in water, water can be poured into the reactor vessel 20, a safety water supplementing valve 24 is arranged between two ends of the safety water supplementing pipe 23, and the safety water supplementing valve 24 controls the conduction of the safety water supplementing pipe 23, so that the water supplementing in the reactor vessel 20 is controlled.
When an accident occurs in the reactor, the safety water supplementing valve 24 is opened, if the pressure in the reactor vessel 20 is smaller than the pressure at the free end of the safety water supplementing pipe 23 in the water tank 10, the water flow in the water tank 10 enters the reactor vessel 20 under the action of hydrostatic pressure, so that the temperature of the reactor core in the reactor vessel 20 can be reduced, and the damage influence caused by the accident can be reduced.
The operation of the nuclear reactor safety system 100 according to an embodiment of the present invention is described below with reference to specific embodiments.
A nuclear reactor safety system 100 according to an embodiment of the present invention includes: the reactor comprises a water tank 10, a reactor vessel 20, a reactor core, a first heat exchanger 30, a passive waste heat exchanger 40 and a first isolation valve 50, wherein the reactor vessel 20 is arranged in the water tank 10 and is positioned below the liquid level in the water tank 10, the reactor vessel 20 is provided with a vessel inlet 21 and a vessel outlet 22, the reactor core is positioned in the reactor vessel 20, the first heat exchanger 30 is positioned outside the reactor vessel 20, the first heat exchanger 30 is connected with the vessel inlet 21 and the vessel outlet 22 of the reactor vessel 20 to form a closed first loop, the first heat exchanger 30 is connected with a heat supply network, water in the reactor vessel 20 exchanges heat with water in the heat supply network through the first heat exchanger 30, the passive waste heat exchanger 40 is arranged in the water tank 10 and is positioned below the liquid level in the water tank 10, the passive waste heat exchanger 40 is connected with the first loop and is used for leading heat in the first loop into the water tank 10 when an accident occurs, the first isolation valve 50 is arranged on a pipeline between the passive heat exchanger 40 and the first loop, and the first isolation valve 50 is closed when the reactor is in normal operation.
When a non-break accident occurs in the pool type heating reactor, the first isolation valve 50 is opened to conduct the pipeline between the passive waste heat exchanger 40 and the first loop, the two ports of the passive waste heat exchanger 40 are respectively communicated with the container inlet 21 and the container outlet 22 of the reactor container 20 by using the connection function of the first loop, heat exchange between the passive waste heat exchanger 40 and the reactor container 20 is realized by the circulation of cooling liquid in the communication pipeline, and heat in the pool 10 is discharged by using the mutual cooperation between the built-in heat exchanger 60 and the external heat exchanger 61, so that the serious accident caused by continuous rising of the temperature and the pressure in the reactor container is prevented.
If the pool type heating reactor has a break accident, the reactor core is not exposed due to massive loss and evaporation of the coolant even if the main loop of the reactor is damaged due to lower temperature and pressure of the first loop, the safety water supplementing valve 24 on the safety water supplementing pipe 23 is opened, water in the pool enters the reactor container 20, and the low-temperature micro-pressure characteristic enables the reactor to have the condition of reducing the equipment safety level.
According to the nuclear reactor safety system 100 of the embodiment of the invention, the reactor vessel 20 is arranged in the pool 10, the first heat exchanger 30 is communicated by the pipeline, heat generated by the core reaction in the inner cavity of the reactor vessel 20 is transmitted to other equipment for supplying heat, the passive waste heat exchanger 40 communicated with the reactor vessel 20 is arranged in the pool 10, the first isolation valve 50 is used for controlling the conduction of the pipeline between the passive waste heat exchanger 40 and the first loop, normal operation and heat supply of the pool type heat supply reactor can be ensured, the safety performance of the pool type heat supply reactor can be improved, when the pool type heat supply reactor has an accident, the heat in the reactor vessel 20 is transmitted to the pool 10 by the passive waste heat exchanger 40, the heat emitted by the pool type heat supply reactor is absorbed by water in the pool 10, the pool type heat supply reactor accident is prevented from inducing a larger safety accident, the pool type heat supply reactor safety system 100 has simple structure and low cost, the core leakage can be prevented, and the hazard degree of the accident is also reduced.
In summary, the pool type heating reactor according to the embodiment of the invention mainly comprises three circulation loops and a safety system, wherein the first loop is a coolant loop, and the coolant is taken as a carrier to effectively guide out the reactor core fission energy; the second loop is a radioactive isolation loop and plays a role of an additional heat trap; the third loop is a heat supply loop and is connected with a heat source user pipe network. The three circulation loops effectively guide out the energy generated by fission in the reactor core for the urban heating system.
The first loop is composed mainly of a reactor body and a reactor coolant system. The reactor body structure consists of a reactor container, a reactor core, a reactor inner member, a control rod driving mechanism and the like. The reactor core is positioned in a reactor vessel which is submerged in a deep well, and the pressure in the reactor vessel is higher than that of a pool reactor in which the reactor core is directly submerged in a pool, so that the heat supply parameters of the reactor vessel are improved. Moreover, the pool water within the well in the system provides a large intermediate heat sink for the removal of core waste heat during an accident, as compared to a shell reactor, an important mitigation measure for the reactor accident. The upper part and the lower part of the reactor core are respectively provided with a cavity. The control rod drive mechanism is located above the core.
The reactor coolant system consists of several loops, each loop consisting of the primary side of the primary plate heat exchanger, the main pump and associated piping, valves, etc. The reactor inlet pipe is connected to the lower part of the core pressure vessel, that is, the lower chamber is connected to several cold pipes. Compared with the prior pressurized water reactor technology, the reactor vessel of the system is submerged in a water tank, the pressure vessel can be provided with no descending section, the equipment is simplified, and the resistance of the coolant is reduced. The reactor outlet pipe is connected to the upper part of the reactor vessel, that is, the upper reactor chamber is connected to a plurality of heat pipes.
The pool heating reactor is provided with a second loop connecting the coolant loop to the municipal heating network. The second loop is composed of a plurality of loops, and each loop is composed of a secondary side of the primary heat exchanger, a primary side of the secondary heat exchanger, a circulating pump, a voltage stabilizer, corresponding pipelines and valves. The second loop isolates the reactor coolant loop from the municipal heating pipeline, so that radioactivity cannot be brought to the municipal heating network under any accident condition. The pressure of the working medium in the second loop is slightly higher than that of the first loop, and under the accident working condition, the coolant in the first loop cannot leak to the second loop so as to avoid radioactive pollution to the working medium in the second loop; the second loop simultaneously plays a role of an additional heat trap, and can partially lead out the core waste heat under certain accident working conditions.
The pool type heat supply reactor is also provided with three loops which are connected with a heat supply pipe network of a city. The third loop is composed of one or a plurality of loops, and each loop is composed of the secondary side of the secondary heat exchanger, a constant pressure pump, a circulating pump, corresponding pipelines and valves.
In addition, a pressure stabilizer is also arranged on the reactor coolant system, and the internal pressure of the pressure stabilizer is regulated through heating by an electric heater and spraying by a sprayer. The pressure stabilizer is connected with the pressure relief box, and the connecting pipeline is provided with a pressure relief valve and a safety valve. When the pressure of the pressure stabilizer is high to a setting value, the pressure relief valve is opened, and the pressure stabilizer is communicated with the pressure relief box, so that the pressure in the pressure stabilizer is reduced; when the pressure of the pressure stabilizer is higher to a higher setting value, the safety valve is opened, and the pressure stabilizer is communicated with Chi Shuixiang, so that the pressure in the pressure stabilizer is reduced.
The safety system of the pool type heating reactor mainly comprises a pool heat extraction circulation system and an passive waste heat discharge system, wherein the pool heat extraction circulation system consists of a shielding plant outer air cooler, a pool inner heat exchanger, a related pipeline and a valve, the shielding plant outer air cooler is positioned outside the shielding plant, the connecting pipeline penetrates through a containment and maintains the tightness of the containment, air is taken as a final heat trap, the heat exchange between pool water and air is realized, and the pool water is cooled without time limit. When the temperature of the pool water rises to reach a high-temperature setting value, the heat extraction circulation system of the pool is started, fluid in the circulation system is heated and then driven by buoyancy lift force to flow, hot fluid rises to the outside air cooler, density rises under the air cooling, and flows back to the heat exchange tubes in the pool under the action of density difference, so that circulation is formed repeatedly, and decay heat is continuously led out to the environment.
The passive waste heat discharging system consists of a passive waste heat exchanger, a water tank, a check valve, a first isolation valve and a connecting pipeline. The check valve is connected with a cold pipe of the coolant loop, when a break accident occurs, the check valve is automatically opened when the reactor water level is lower than the water level of the pool by a certain height, the pool water enters the reactor to submerge the reactor core, when a non-break accident occurs, the second isolation valve is closed, the first actuator is isolated, meanwhile, the first isolation valve is opened, the passive waste heat exchanger and the reactor core are communicated, and water or steam above the reactor core enters the passive waste heat exchanger to exchange heat with the pool water for cooling.
The temperature and pressure of the coolant in the micro-pressurized well type reactor of the pool type heating reactor are lower, and the reactor core is not exposed due to massive loss and evaporation of the coolant when the main loop of the reactor is damaged. The low-temperature micro-pressure characteristic enables the device to have the condition of reducing the safety level of the device, and is beneficial to reducing the manufacturing cost of the device.
The reactor vessel does not have a drop section, the equipment is simplified, and the resistance to the coolant is reduced. The plate heat exchanger is adopted, the structure is compact, and the maintenance cost is low. Compared with the traditional pressurized water reactor nuclear power plant, the reactor core adopts a boron-free scheme, so that a capacity melting system applied in the traditional power plant is simplified, and the operation process flow is simplified. The heat removal circulation system of the pool is adopted, circulation is formed under the action of density difference, decay heat is continuously led out to the environment, and the safety guarantee is not limited in time. The low pressure low temperature operating characteristics of the reactor coolant system, the passive characteristics of the safety system, the huge heat release capacity of the deepwater pool and the air cooling circulation take the atmosphere as a final heat sink to remove decay heat in the pool, so that the design scheme can ensure the inherent safety of the reactor and practically eliminate the reactor core failure risk.
Other constructions and operations of the pool heating reactor according to embodiments of the present invention are known to those of ordinary skill in the art and will not be described in detail herein.
In the description of the present invention, it should be understood that the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", etc. indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings are merely for convenience in describing the present invention and simplifying the description, and do not indicate or imply that the devices or elements referred to must have a specific orientation, be configured and operated in a specific orientation, and thus should not be construed as limiting the present invention.
Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include one or more such feature. In the description of the present invention, the meaning of "a plurality" is two or more, unless explicitly defined otherwise.
In the present invention, unless explicitly specified and limited otherwise, the terms "mounted," "connected," "secured," and the like are to be construed broadly and may be, for example, fixedly connected, detachably connected, or integrally connected; can be mechanically or electrically connected; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present invention can be understood by those of ordinary skill in the art according to the specific circumstances.
In the present invention, unless expressly stated or limited otherwise, a first feature "above" or "below" a second feature may include both the first and second features being in direct contact, as well as the first and second features not being in direct contact but being in contact with each other through additional features therebetween. Moreover, a first feature being "above," "over" and "on" a second feature includes the first feature being directly above and obliquely above the second feature, or simply indicating that the first feature is higher in level than the second feature. The first feature being "under", "below" and "beneath" the second feature includes the first feature being directly above and obliquely above the second feature, or simply indicating that the first feature is less level than the second feature.
In the description of the present specification, a description referring to terms "one embodiment," "some embodiments," "examples," "specific examples," or "some examples," etc., means that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present invention. In this specification, schematic representations of the above terms do not necessarily refer to the same embodiments or examples. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples.
Although embodiments of the present invention have been shown and described above, it will be understood that the above embodiments are illustrative and not to be construed as limiting the invention, and that variations, modifications, alternatives, and variations may be made in the above embodiments by those skilled in the art without departing from the spirit and principles of the invention.
Claims (8)
1. A nuclear reactor safety system, comprising:
a water pool, a water pool,
a reactor vessel disposed within the pool and below a liquid level within the pool, the reactor vessel having a vessel inlet and a vessel outlet;
a core located within the reactor vessel;
a first heat exchanger located outside the reactor vessel, the first heat exchanger being connected to a vessel inlet and a vessel outlet of the reactor vessel to form a closed first loop, the first heat exchanger being adapted to be connected to a heating network, water within the reactor vessel being heat exchanged with water within the heating network via the first heat exchanger;
the passive waste heat exchanger is arranged in the water tank and is positioned below the liquid level in the water tank, and the passive waste heat exchanger is connected with the first loop and is used for guiding heat in the first loop into the water tank when an accident occurs in the reactor;
a first isolation valve provided on a pipe between the passive waste heat exchanger and the first circuit, the first isolation valve being closed when the reactor is normally operated and opened when an accident occurs in the reactor;
the built-in heat exchanger is arranged in the water tank and is positioned below the liquid level in the water tank;
the external heat exchanger is arranged outside the water tank and used for guiding out heat in the water tank;
the safety water supplementing pipe is arranged in the water tank, the safety water supplementing valve is arranged on the safety water supplementing pipe, one end of the safety water supplementing pipe is communicated with the reactor container, the other end of the safety water supplementing pipe is communicated with the water tank, and the safety water supplementing valve is opened when an accident occurs in the reactor and the pressure in the reactor container is lower than the pressure in the water tank, so that water in the water tank is injected into the reactor container.
2. The nuclear reactor safety system of claim 1, further comprising: the containment, the pond is established in the containment, external heat exchanger is established outside the containment.
3. The nuclear reactor safety system of claim 2, further comprising: the loop voltage stabilizer is arranged in the containment and is positioned outside the water pool, the loop voltage stabilizer is connected with the first loop to adjust the pressure in the first loop, and the loop voltage stabilizer sends out a signal for controlling the opening of the first isolation valve when a non-break accident occurs in the reactor and the pressure in the loop voltage stabilizer is higher than a preset value.
4. The nuclear reactor safety system of claim 1, further comprising: the reservoir, the reservoir with the pond intercommunication is used for to the moisturizing in the pond.
5. The nuclear reactor safety system of claim 4, wherein a pressure in a circuit between the first heat exchanger and the heating network is greater than a pressure in the first circuit.
6. The nuclear reactor safety system according to any one of claims 1-5, wherein the pressure within the first circuit is 1.5-20 standard atmospheres.
7. The nuclear reactor safety system of claim 6, wherein the pressure within the first circuit is 5-12 atmospheres gauge.
8. The nuclear reactor safety system of claim 7, wherein the pressure within the first circuit is 6-9 atmospheres gauge.
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| CN201620302992 | 2016-04-12 | ||
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| CN2016205897304 | 2016-06-16 | ||
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| CN107293338A CN107293338A (en) | 2017-10-24 |
| CN107293338B true CN107293338B (en) | 2023-06-23 |
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| CN201610862925.6A Active CN107293341B (en) | 2016-04-12 | 2016-09-28 | Pool type reactor |
| CN201621089913.6U Active CN206210415U (en) | 2016-04-12 | 2016-09-28 | Pool heat reactor |
| CN201610862926.0A Active CN107293338B (en) | 2016-04-12 | 2016-09-28 | Nuclear reactor safety system |
| CN201621089894.7U Active CN206210405U (en) | 2016-04-12 | 2016-09-28 | Nuclear reactor safety system |
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| CN201610862925.6A Active CN107293341B (en) | 2016-04-12 | 2016-09-28 | Pool type reactor |
| CN201621089913.6U Active CN206210415U (en) | 2016-04-12 | 2016-09-28 | Pool heat reactor |
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| CN206210418U (en) * | 2016-04-12 | 2017-05-31 | 国家电投集团科学技术研究院有限公司 | Pool reactor |
| CN108320817B (en) * | 2017-12-28 | 2019-12-20 | 中核北方核燃料元件有限公司 | Air pressure sealing method |
| CN108443850A (en) * | 2018-03-29 | 2018-08-24 | 何满潮 | Waste heat collection and utilization system for underground neutron energy power station |
| CN108550407A (en) * | 2018-03-30 | 2018-09-18 | 清华大学天津高端装备研究院 | A kind of lead bismuth heap primary Ioops system and nuclear reactor |
| CN108417282A (en) * | 2018-05-11 | 2018-08-17 | 上海核工程研究设计院有限公司 | A kind of loop structure of reactor circuit and a kind of low-temperature heat supply reactor with the reactor circuit |
| CN108665981A (en) * | 2018-07-03 | 2018-10-16 | 启迪新核（北京）能源科技有限公司 | The natural circulation cooling system and well formula normal pressure process heat reactor of well formula normal pressure process heat reactor |
| CN108877962A (en) * | 2018-07-11 | 2018-11-23 | 上海核工程研究设计院有限公司 | A kind of pool integrated low-temperature reactor heating system |
| CN109559836A (en) * | 2018-10-30 | 2019-04-02 | 中广核研究院有限公司 | A kind of method that nuclear power station is improved based on the chemical environment of water of no soluble boron coolant |
| CN109545402A (en) * | 2018-10-30 | 2019-03-29 | 中广核研究院有限公司 | A kind of method that nuclear power station is adjusted based on the chemical environment of water of no soluble boron coolant |
| CN111383782B (en) * | 2018-12-28 | 2022-12-23 | 国家电投集团科学技术研究院有限公司 | Passive safety system and pressurized water reactor with same |
| CN111383786B (en) * | 2018-12-29 | 2022-08-30 | 国家电投集团科学技术研究院有限公司 | Method for changing material of pool reactor |
| CN111883270B (en) * | 2020-08-26 | 2023-05-23 | 中国原子能科学研究院 | Heat discharging system, pool type reactor and pool type reactor heat discharging method |
| CN112216412B (en) * | 2020-09-04 | 2023-11-03 | 国家电投集团科学技术研究院有限公司 | Passive self-regulating waste heat lead-out system, method and liquid metal reactor |
| CN112071454B (en) * | 2020-09-15 | 2023-01-03 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
| CN114914001A (en) * | 2021-02-07 | 2022-08-16 | 华龙国际核电技术有限公司 | Nuclear power station cooling system |
| CN114999683B (en) * | 2022-06-16 | 2024-09-24 | 中广核研究院有限公司 | Integrated safety system for a reactor |
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Also Published As
| Publication number | Publication date |
|---|---|
| CN107293341B (en) | 2023-11-03 |
| CN107293338A (en) | 2017-10-24 |
| CN206210418U (en) | 2017-05-31 |
| CN206210405U (en) | 2017-05-31 |
| CN107293341A (en) | 2017-10-24 |
| CN206210415U (en) | 2017-05-31 |
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