CN109166637B - ORC-based pressurized water reactor nuclear power station nuclear safety system and method - Google Patents
ORC-based pressurized water reactor nuclear power station nuclear safety system and method Download PDFInfo
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- CN109166637B CN109166637B CN201810826104.6A CN201810826104A CN109166637B CN 109166637 B CN109166637 B CN 109166637B CN 201810826104 A CN201810826104 A CN 201810826104A CN 109166637 B CN109166637 B CN 109166637B
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 124
- 238000000034 method Methods 0.000 title claims abstract description 14
- 239000000498 cooling water Substances 0.000 claims abstract description 151
- 239000002826 coolant Substances 0.000 claims abstract description 83
- 238000001816 cooling Methods 0.000 claims abstract description 10
- 239000007788 liquid Substances 0.000 claims description 25
- 238000004146 energy storage Methods 0.000 claims description 10
- 230000005484 gravity Effects 0.000 claims description 10
- 239000003381 stabilizer Substances 0.000 claims description 6
- 238000002844 melting Methods 0.000 abstract description 6
- 230000008018 melting Effects 0.000 abstract description 6
- 238000003912 environmental pollution Methods 0.000 abstract description 4
- 239000003758 nuclear fuel Substances 0.000 abstract description 4
- 239000002918 waste heat Substances 0.000 description 11
- 238000006243 chemical reaction Methods 0.000 description 5
- 238000013461 design Methods 0.000 description 3
- 239000012530 fluid Substances 0.000 description 3
- 239000007789 gas Substances 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 230000000630 rising effect Effects 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
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- 230000007613 environmental effect Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000008239 natural water Substances 0.000 description 1
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- 238000010248 power generation Methods 0.000 description 1
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- 229920006395 saturated elastomer Polymers 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
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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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Abstract
ORC-based pressurized water reactor nuclear power station nuclear safety system and method, comprising: a cooling water circuit, an organic rankine cycle ORC circuit, and a coolant circuit located within the nuclear island; the cooling water circuit is used for transferring heat absorbed from the coolant circuit to the ORC circulation circuit; the ORC circulation loop is used for providing power for the cooling water loop and power equipment dispersed in the nuclear safety system; the coolant loop is used for exchanging heat with a nuclear reactor, cooling the nuclear reactor and transferring heat provided by the nuclear reactor to the cooling water loop. The invention can effectively prevent serious nuclear safety accidents such as reactor core temperature surge, reactor core melting, nuclear fuel leakage and the like caused by natural disasters and other irresistible factors and lack of power sources of the cooling water pump, provides a guarantee for the safety of the pressurized water reactor nuclear power station, and furthest avoids environmental pollution and economic loss caused by nuclear leakage.
Description
Technical Field
The invention relates to the field of energy power, in particular to a pressurized water reactor nuclear power station nuclear safety system and method based on ORC.
Background
As clean and efficient high-quality energy, nuclear power has important significance for optimizing energy structures and guaranteeing national energy safety, but different from conventional energy, nuclear fuel has radioactive and radioactive physical characteristics, and the safety design and operation of nuclear reactors are critical to nuclear power development planning. At present, most nuclear power plants are pressurized water reactors, and potential safety hazards still exist although passive safety designs and the like are added to safety systems of the nuclear power plants. The important point of the safety of the nuclear power plant is that cooling water is conveyed to the reactor core, and the reaction waste heat is cooled down, so that the reactor core is prevented from melting and nuclear fuel is prevented from leaking. However, when natural disasters such as earthquake and tsunami occur, the power of the cooling water conveying pump cannot be ensured due to large-area power failure, damage of standby facilities and the like.
Disclosure of Invention
In order to solve the above-mentioned shortcomings existing in the prior art, the present invention provides a nuclear safety system and method of pressurized water reactor. Because the reaction waste heat after the nuclear power station is shut down is a resource capable of generating power, and in the waste heat-to-power conversion technology, an Organic RANKINE CYCLE, ORC system has the characteristics of wide applicable temperature range, simple structure, high efficiency and the like, so that the pressurized water reactor nuclear safety system based on ORC circulation is designed, the reactor waste heat is utilized to provide power for a cooling water pump, the surplus energy is converted into electric energy, and auxiliary power is provided for power equipment dispersed in the safety system, thereby providing a guarantee for the safety of the pressurized water reactor.
The technical scheme provided by the invention is as follows: an ORC-based pressurized water reactor nuclear power plant nuclear safety system, comprising:
a cooling water circuit, an organic rankine cycle ORC circuit, and a coolant circuit located within the nuclear island;
The cooling water circuit is used for transferring heat absorbed from the coolant circuit to the ORC circulation circuit;
the ORC circulation loop is used for providing power for the cooling water loop and power equipment dispersed in the nuclear safety system;
the coolant loop is used for exchanging heat with a nuclear reactor, cooling the nuclear reactor and transferring heat provided by the nuclear reactor to the cooling water loop.
Preferably, the ORC circulation circuit comprises:
The system comprises an organic steam generator, a main expander, a condenser, a liquid storage tank and an organic working medium pump;
The organic steam generator is used for transferring heat in the cooling water loop to the ORC circulating loop so as to heat organic working medium in the ORC circulating loop into organic steam;
The main expander is connected with the organic steam generator and is used for providing power for the cooling water loop;
The top end interface of the condenser is connected with the main expander and is used for absorbing the heat of the organic steam in the ORC circulation loop by utilizing the cooling water loop;
the inlet of the liquid storage tank is connected with the condenser, and the outlet of the liquid storage tank is connected with the organic working medium pump and is used for storing organic working medium;
the organic working medium pump is connected with the organic steam generator and is used for providing power for the organic working medium and entering the organic steam generator from the liquid storage tank.
Preferably, the ORC circulation circuit further comprises:
An auxiliary expander and a valve;
the auxiliary expander is connected with the organic steam generator after being connected with the main expanding agent in parallel, and is connected with the generator, and is used for driving the generator to generate power by utilizing the heat of the organic steam in the ORC circulation loop so as to supply power for power equipment dispersed in the nuclear safety system;
The valve is arranged on a pipeline between the organic steam generator and the auxiliary expander and is used for controlling the distribution of the organic steam flow in the ORC circulation loop through the opening degree of the valve.
Preferably, the cooling water circuit includes:
A water source, a cooling water pump and a water vapor generator;
The water source is used for providing cooling water;
The cooling water pump is positioned beside the water source and connected with the main expansion machine to provide power for drawing cooling water;
The water vapor generator is positioned in the nuclear island and is connected with the organic vapor generator, a spiral coolant pipeline is sleeved in the water vapor generator, and the coolant pipeline is used for connecting a reactor core heat exchanger in a reactor core.
Preferably, the coolant loop is composed of a coolant pump, a core heat exchanger and a pressure stabilizer which are sequentially connected in series with the water vapor generator.
Preferably, the nuclear security system further comprises:
Three water turbines and a gravity water storage tower;
the first water turbine is connected with the cooling water pump, the second water turbine is connected with the cooling water pump, and the third water turbine is connected with the organic working medium pump;
The water turbine is used for providing kinetic energy for the cooling water pump, the coolant pump and the organic working medium pump when the nuclear safety system is started;
the gravity water storage tower is communicated with the three water turbines through pipelines and is used for providing energy storage water for the water turbines when the nuclear safety system is started.
Preferably, the organic vapor generator is a plate heat exchanger.
Based on the same inventive concept, the invention also provides a method for cooling a nuclear safety system based on a pressurized water reactor nuclear power station, which comprises the following steps:
The coolant loop absorbs heat from the nuclear reactor, cools the nuclear reactor, and transfers heat provided by the nuclear reactor to the cooling water loop;
the cooling water circuit transfers heat absorbed from the coolant circuit to the ORC circulation circuit;
The ORC circulation loop powers the cooling water loop and also powers power plants dispersed in the nuclear safety system.
Preferably, the ORC circulation circuit powers the cooling water circuit, comprising:
The organic working medium in the ORC circulation loop enters the organic steam generator from the liquid storage tank under the drive of the organic working medium pump;
The organic working medium in the organic steam generator absorbs heat released by water vapor in the cooling water loop to generate organic steam;
And the organic steam enters a main expander in the ORC circulation loop to do work and provide power for a cooling water pump in a cooling water loop.
Preferably, the power device for powering the power plant dispersed in the nuclear safety system comprises:
the organic steam enters an auxiliary expander in the ORC circulation loop according to a preset valve opening to do work;
The auxiliary expander drives the generator to generate power, and provides power for power equipment dispersed in the nuclear safety system.
Preferably, the cooling water circuit transfers heat absorbed from the coolant circuit to the ORC circulation circuit, comprising:
a cooling water pump in the cooling water loop pumps cooling water in a water source to a condenser in the ORC circulation loop;
The cooling water is conveyed to a water vapor generator through the condenser;
the cooling water in the water vapor generator absorbs heat of the coolant in the coolant loop to generate water vapor;
the water vapor enters an organic vapor generator in the ORC circulation loop, transfers heat to an organic working medium and condenses the heat into liquid water;
the liquid water is returned to the water source.
Preferably, the cooling water is sent to the water vapor generator through the condenser, and the cooling water includes:
the cooling water passing in the condenser provides a cold trap for the ORC circulation loop, condensing the exhaust gases in the main and auxiliary expanders into liquid.
Preferably, the coolant circuit absorbs heat from the nuclear reactor, cools the nuclear reactor, and transfers heat provided by the nuclear reactor to the cooling water circuit, comprising:
A coolant pump in the coolant loop sends coolant into the core, absorbs heat from the nuclear reactor, and cools the nuclear reactor;
The coolant is pumped back to the core by the coolant after the coolant cools the cooling water in the water vapor generator by the pressure stabilizer.
Preferably, the method further comprises:
When the pressurized water reactor nuclear power station has an accident, when the nuclear safety system is started, a gravity water storage tower provides energy storage water for three water turbines respectively arranged beside a cooling water pump, a coolant pump and an organic working medium pump;
The three water turbines respectively utilize the energy storage water to provide power for a cooling water pump, a coolant pump and an organic working medium pump;
when the ORC circulation loop is operated, the power sources of the cooling water pump, the cooling water pump and the organic working medium pump are switched into the ORC circulation loop by three water turbines.
Compared with the closest prior art, the technical scheme provided by the invention has the following beneficial effects:
The technical scheme provided by the invention comprises a cooling water loop, an Organic Rankine Cycle (ORC) loop and a coolant loop positioned in a nuclear island; the cooling water circuit is used for transferring heat absorbed from the coolant circuit to the ORC circulation circuit; the ORC circulation loop is used for providing power for the cooling water loop and power equipment dispersed in the nuclear safety system; the coolant loop is used for carrying out heat exchange with the nuclear reactor, cooling the nuclear reactor and transmitting the heat provided by the nuclear reactor to the cooling water loop, so that serious nuclear safety accidents such as core temperature surge, core melting and nuclear fuel leakage caused by lack of power sources of the cooling water pump under the condition of unreliability factors such as natural disasters can be effectively prevented, and the safety of the pressurized water reactor nuclear power station is ensured, so that environmental pollution and economic loss caused by nuclear leakage are avoided to the greatest extent.
According to the technical scheme provided by the invention, the ORC is used for circularly utilizing the core waste heat to provide power for the cooling water pump, so that the cooling water is driven to cool the nuclear reactor core, and the self-sufficiency of the power of the nuclear safety system is realized.
According to the technical scheme provided by the invention, the higher the temperature of the reactor core is, the more power is generated by ORC circulation, and the cooling water pump is driven to supply more cooling water to cool the reactor core, so that self-adaptive negative feedback is established between the temperature of the reactor core and the flow rate of the cooling water.
According to the technical scheme provided by the invention, the two parallel expanders are arranged, and the distribution of the organic steam flow is controlled through the opening of the valve, so that the distribution of the power of the cooling water pump and the power generation amount of the generator is controlled.
According to the technical scheme provided by the invention, the ORC circulation loop preferably adopts a mixed organic working medium so as to adapt to the characteristic that the temperature of the waste heat of the reactor core changes along with time, and the higher energy conversion efficiency is kept.
According to the technical scheme provided by the invention, the coolant loop utilizes the pressurized water coolant system of the nuclear island, so that the structure and equipment of the safety system are simplified, the reliability is improved, and meanwhile, nuclear substances of the reactor core are prevented from entering an environmental cooling water source through the cooling water open circulation loop.
According to the technical scheme provided by the invention, power equipment such as a cooling water pump in a cooling water loop, a cooling water pump in a cooling agent loop, an organic working medium pump in an ORC loop and the like are provided with passive power sources so as to realize the starting of a nuclear safety system.
According to the technical scheme provided by the invention, when the nuclear safety system is started, the gravity water storage tower is used for supplying the energy storage water with gravity force in a central concentrated supply mode, so that the structure of the nuclear safety system is simplified, and meanwhile, the reliability of the nuclear safety system is improved.
Drawings
FIG. 1 is a schematic diagram of a nuclear safety system of an ORC-based pressurized water reactor nuclear power plant;
Wherein, 1-cooling water source; 2-a cooling water pump; 3-nuclear islands; 4-a water vapor generator; 5-coolant pump; 6-core; 7-a voltage stabilizer; 8-an organic steam generator; 9-an organic working fluid reservoir; 10-an organic working fluid pump; 11-a main expander; 12-regulating valve; 13-an auxiliary expander; a 14-generator; 15-condenser.
Detailed Description
For a better understanding of the present invention, reference is made to the following description, drawings and examples.
The embodiment provides a pressurized water reactor nuclear power station nuclear safety system based on ORC. After nuclear accident and shutdown, the reactor still emits a large amount of waste heat, and cooling water needs to be pumped in to cool the reactor so as to prevent the melting of the reactor core and the leakage of the reactor core. However, under the factors of unreliability such as natural disasters, the power source of the cooling water pump cannot be guaranteed. The pressurized water reactor nuclear safety system is built based on Organic Rankine Cycle (ORC), waste heat of the reactor is ingeniously utilized, the waste heat is converted into power of a cooling water pump, and surplus energy is converted into electric energy for power equipment dispersed in the safety system, so that cooling water supply and cooling of a reactor core are guaranteed, and self-sufficiency of power of the nuclear safety system is achieved.
Meanwhile, the system provided by the embodiment establishes self-adaptive negative feedback between the temperature of the reactor core and the flow of cooling water: the higher the core temperature, the more power the ORC cycle produces, driving the cooling water pump to supply more cooling water to cool the core, thereby preventing the core temperature from rising and melting.
Therefore, the system provided by the embodiment provides a guarantee for the safety of the pressurized water reactor, and the environmental pollution and economic loss caused by nuclear leakage are avoided to the greatest extent.
As shown in fig. 1, the nuclear safety system of the pressurized water reactor nuclear power plant comprises: a cooling water circuit, an organic rankine cycle ORC circuit, and a coolant circuit located within the nuclear island;
The cooling water circuit is used for transferring heat absorbed from the coolant circuit to the ORC circulation circuit;
the ORC circulation loop is used for providing power for the cooling water loop and power equipment dispersed in the nuclear safety system;
the coolant loop is used for exchanging heat with a nuclear reactor, cooling the nuclear reactor and transferring heat provided by the nuclear reactor to the cooling water loop.
In this embodiment, a natural water source such as a river, a lake or the like is used as a cooling water source 1 for a safety system, and a cooling water pump 2 draws cooling water from the cooling water source 1 and delivers the cooling water to a nuclear island 3. In the water vapor generator 4 in the nuclear island 3, the cooling water is heated to saturated vapor. The working medium for heating the cooling water comes from the high-temperature coolant after the coolant pump 5 transmits the heat to the cooling water, and then the cooling water is cooled and is transmitted back to the reactor core 6 by the coolant pump 5 again, so that a coolant loop is formed. The coolant circuit maintains the coolant in a liquid state by the pressurizer 7, and dry combustion can be prevented when the core exchanges heat with the coolant. Therefore, the cooling water in the nuclear island 3 exchanges heat with the reactor core 6 in an indirect manner, which is beneficial to avoiding the leakage of nuclear radiation substances of the reactor core 6 and causing environmental pollution.
The steam generated by the steam generator 4 enters the organic steam generator 8, transfers heat to the organic working medium and condenses into liquid water, and then is discharged back into the cooling water source 1 to form an open loop.
Under the drive of an organic working medium pump 10, the organic working medium enters the organic steam generator 8 from the organic working medium liquid storage tank 9, absorbs the heat released by the water vapor to generate organic steam, and enters the main expander 11 to apply work so as to provide power for the cooling water pump 2.
Under the condition that the organic steam carries energy in a surplus way, the valve 12 allows part of the organic steam to enter the auxiliary expander 13 at a certain opening degree to drive the generator 14 to generate electric energy so as to provide power for the coolant pump 5, the organic working medium pump 10 and the like which are distributed at other places of the safety system.
The low-energy organic working medium exhaust gas at the outlets of the main expander and the auxiliary expander enters the condenser 15, and the cooling water provided by the cooling water pump 2 is cooled into a liquid state and returns to the organic working medium liquid storage tank 9, so that a complete ORC closed cycle is formed.
The ORC circulation loop preferably adopts a mixed organic working medium so as to adapt to the characteristic that the temperature of the waste heat of the reactor core changes along with time, and the high energy conversion efficiency is maintained.
Through the mode, the ORC circularly utilizes the waste heat of the reactor core, provides power for the cooling water pump, the coolant pump and the organic working fluid pump, and realizes self-sufficiency of power of the nuclear safety system.
Meanwhile, the higher the temperature of the reactor core 6 is, the higher the temperature and pressure parameters of organic working medium steam generated in the organic steam generator 8 are, the more power is generated through the main expander 11, and the cooling water pump 2 is driven to supply more cooling water to cool the reactor core, so that self-adaptive negative feedback is established between the temperature of the reactor core and the flow of the cooling water, the temperature of the reactor core can be effectively prevented from rising and melting, and the safety of the reactor core under a nuclear accident is ensured.
Starting the pressurized water reactor nuclear safety system by utilizing ORC waste heat, and adopting passive safety design: the safety system is provided with water turbines for cooling the water pump 2, the coolant pump 5 and the organic working medium pump 10, and the gravity water storage tower is used for intensively supplying energy storage water during starting, and gravitational potential energy is converted into power of the cooling water pump 2, the coolant pump 5 and the organic working medium pump 10 through the water turbines. After the ORC cycle normally operates, the power sources of the cooling water pump 2, the coolant pump 5 and the organic working medium pump 10 are switched into mechanical energy and electric energy provided by the ORC main expander 11 and the generator 14 by the standby water turbine.
Based on the same inventive concept, the embodiment also provides a method for cooling a pressurized water reactor nuclear power station nuclear safety system based on ORC, comprising the following steps:
The coolant loop absorbs heat from the nuclear reactor, cools the nuclear reactor, and transfers heat provided by the nuclear reactor to the cooling water loop;
the cooling water circuit transfers heat absorbed from the coolant circuit to the ORC circulation circuit;
The ORC circulation loop powers the cooling water loop and also powers power plants dispersed in the nuclear safety system.
In an embodiment, the ORC circulation circuit powers the cooling water circuit, comprising:
The organic working medium in the ORC circulation loop enters the organic steam generator from the liquid storage tank under the drive of the organic working medium pump;
The organic working medium in the organic steam generator absorbs heat released by water vapor in the cooling water loop to generate organic steam;
And the organic steam enters a main expander in the ORC circulation loop to do work and provide power for a cooling water pump in a cooling water loop.
In an embodiment, the method for powering a power plant dispersed in a nuclear safety system comprises:
the organic steam enters an auxiliary expander in the ORC circulation loop according to a preset valve opening to do work;
The auxiliary expander drives the generator to generate power, and provides power for power equipment dispersed in the nuclear safety system.
In an embodiment, the cooling water circuit transfers heat absorbed from the coolant circuit to the ORC circulation circuit, comprising:
a cooling water pump in the cooling water loop pumps cooling water in a water source to a condenser in the ORC circulation loop;
The cooling water is conveyed to a water vapor generator through the condenser;
the cooling water in the water vapor generator absorbs heat of the coolant in the coolant loop to generate water vapor;
the water vapor enters an organic vapor generator in the ORC circulation loop, transfers heat to an organic working medium and condenses the heat into liquid water;
the liquid water is returned to the water source.
In an embodiment, the cooling water is delivered to the water vapor generator through the condenser, comprising:
the cooling water passing in the condenser provides a cold trap for the ORC circulation loop, condensing the exhaust gases in the main and auxiliary expanders into liquid.
In an embodiment, the coolant loop absorbs heat from a nuclear reactor, cools the nuclear reactor, and transfers heat provided by the nuclear reactor to a cooling water loop, comprising:
A coolant pump in the coolant loop sends coolant into the core, absorbs heat from the nuclear reactor, and cools the nuclear reactor;
The coolant is pumped back to the core by the coolant after the coolant cools the cooling water in the water vapor generator by the pressure stabilizer.
In an embodiment, the method further comprises:
When the pressurized water reactor nuclear power station has an accident, when the nuclear safety system is started, a gravity water storage tower provides energy storage water for three water turbines respectively arranged beside a cooling water pump, a coolant pump and an organic working medium pump;
The three water turbines respectively utilize the energy storage water to provide power for a cooling water pump, a coolant pump and an organic working medium pump;
when the ORC circulation loop is operated, the power sources of the cooling water pump, the cooling water pump and the organic working medium pump are switched into the ORC circulation loop by three water turbines.
The foregoing is illustrative of the present invention and is not to be construed as limiting thereof, but rather as providing for the use of additional embodiments and advantages of all such modifications, equivalents, improvements and similar to the present invention are intended to be included within the scope of the present invention as defined by the appended claims.
Claims (6)
1. An ORC-based pressurized water reactor nuclear power plant nuclear safety system, comprising:
a cooling water circuit, an organic rankine cycle ORC circuit, and a coolant circuit located within the nuclear island;
The cooling water circuit is used for transferring heat absorbed from the coolant circuit to the ORC circulation circuit;
the ORC circulation loop is used for providing power for the cooling water loop and power equipment dispersed in the nuclear safety system;
The coolant loop is used for exchanging heat with a nuclear reactor, cooling the nuclear reactor and transmitting heat provided by the nuclear reactor to the cooling water loop;
The ORC circulation circuit includes:
The system comprises an organic steam generator, a main expander, a condenser, a liquid storage tank and an organic working medium pump;
The organic steam generator is used for transferring heat in the cooling water loop to the ORC circulating loop so as to heat organic working medium in the ORC circulating loop into organic steam;
The main expander is connected with the organic steam generator and is used for providing power for the cooling water loop;
The top end interface of the condenser is connected with the main expander and is used for absorbing the heat of the organic steam in the ORC circulation loop by utilizing the cooling water loop;
the inlet of the liquid storage tank is connected with the condenser, and the outlet of the liquid storage tank is connected with the organic working medium pump and is used for storing organic working medium;
The organic working medium pump is connected with the organic steam generator and is used for providing power for the organic working medium and entering the organic steam generator from the liquid storage tank;
The ORC circulation circuit further includes:
An auxiliary expander and a valve;
the auxiliary expander is connected with the organic steam generator after being connected with the main expander in parallel, and is connected with the generator, and is used for driving the generator to generate power by utilizing the heat of the organic steam in the ORC circulation loop so as to supply power for power equipment dispersed in the nuclear safety system;
the valve is arranged on a pipeline between the organic steam generator and the auxiliary expander and is used for controlling the distribution of the organic steam flow in the ORC circulation loop through the opening degree of the valve;
the cooling water circuit includes:
A water source, a cooling water pump and a water vapor generator;
The water source is used for providing cooling water;
The cooling water pump is positioned beside the water source and connected with the main expansion machine to provide power for drawing cooling water;
The water vapor generator is positioned in the nuclear island and connected with the organic vapor generator, and a spiral coolant pipeline is sleeved in the water vapor generator and connects a reactor core heat exchanger in the reactor core;
further comprises: three water turbines and a gravity water storage tower;
The first water turbine is connected with the cooling water pump, the second water turbine is connected with the coolant pump, and the third water turbine is connected with the organic working medium pump;
The organic steam generator is a plate heat exchanger.
2. The pressurized water reactor nuclear power plant nuclear safety system of claim 1 wherein the coolant loop is comprised of a coolant pump, a core heat exchanger, and a pressure stabilizer in series with the water vapor generator.
3. The nuclear security system of a pressurized water reactor nuclear power plant of claim 2,
The water turbine is used for providing kinetic energy for the cooling water pump, the coolant pump and the organic working medium pump when the nuclear safety system is started;
the gravity water storage tower is communicated with the three water turbines through pipelines and is used for providing energy storage water for the water turbines when the nuclear safety system is started.
4. A method of cooling an ORC-based pressurized water reactor nuclear power plant nuclear safety system according to any of claims 1-3, comprising:
The coolant loop absorbs heat from the nuclear reactor, cools the nuclear reactor, and transfers heat provided by the nuclear reactor to the cooling water loop;
the cooling water circuit transfers heat absorbed from the coolant circuit to the ORC circulation circuit;
The ORC circulation loop powers the cooling water loop and also powers power plants dispersed in the nuclear safety system.
5. The method of claim 4, wherein the ORC circulation circuit powers the cooling water circuit, comprising:
The organic working medium in the ORC circulation loop enters the organic steam generator from the liquid storage tank under the drive of the organic working medium pump;
The organic working medium in the organic steam generator absorbs heat released by water vapor in the cooling water loop to generate organic steam;
And the organic steam enters a main expander in the ORC circulation loop to do work and provide power for a cooling water pump in a cooling water loop.
6. The method of any of claims 4-5, wherein powering the power plant dispersed in the nuclear safety system comprises:
the organic steam enters an auxiliary expander in the ORC circulation loop according to a preset valve opening to do work;
The auxiliary expander drives the generator to generate power so as to provide power for power equipment dispersed in the nuclear safety system;
the cooling water circuit transfers heat absorbed from the coolant circuit to the ORC circulation circuit, comprising:
a cooling water pump in the cooling water loop pumps cooling water in a water source to a condenser in the ORC circulation loop;
the cooling water is conveyed to a water vapor generator through the condenser;
the cooling water in the water vapor generator absorbs heat of the coolant in the coolant loop to generate water vapor;
the water vapor enters an organic vapor generator in the ORC circulation loop, transfers heat to an organic working medium and condenses the heat into liquid water;
The liquid water is returned to a water source;
the cooling water is conveyed to a water vapor generator through the condenser, and the cooling water comprises the following components:
The cooling water passing through the condenser provides a cold trap for the ORC circulation loop, condensing the exhaust gas in the main expander and the auxiliary expander into liquid;
the coolant loop absorbs heat from the nuclear reactor, cools the nuclear reactor, and transfers heat provided by the nuclear reactor to a cooling water loop, comprising:
A coolant pump in the coolant loop sends coolant into the core, absorbs heat from the nuclear reactor, and cools the nuclear reactor;
The coolant is pumped back to the reactor core by the coolant after the coolant transfers heat to the cooling water in the water vapor generator through the voltage stabilizer to cool;
The method further comprises the steps of:
When the pressurized water reactor nuclear power station has an accident, when the nuclear safety system is started, a gravity water storage tower provides energy storage water for three water turbines respectively arranged beside a cooling water pump, a coolant pump and an organic working medium pump;
The three water turbines respectively utilize the energy storage water to provide power for a cooling water pump, a coolant pump and an organic working medium pump;
when the ORC circulation loop is operated, the power sources of the cooling water pump, the cooling water pump and the organic working medium pump are switched into the ORC circulation loop by three water turbines.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810826104.6A CN109166637B (en) | 2018-07-25 | 2018-07-25 | ORC-based pressurized water reactor nuclear power station nuclear safety system and method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810826104.6A CN109166637B (en) | 2018-07-25 | 2018-07-25 | ORC-based pressurized water reactor nuclear power station nuclear safety system and method |
Publications (2)
| Publication Number | Publication Date |
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| CN109166637A CN109166637A (en) | 2019-01-08 |
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| CN109707473B (en) * | 2019-02-12 | 2024-07-02 | 郑州欧纳尔冷暖科技有限公司 | ORC circulating pump system |
| CN109879251B (en) * | 2019-03-07 | 2024-05-03 | 南京工程学院 | Hydrogen chloride synthesis system based on energy comprehensive utilization |
| CN110164569A (en) * | 2019-05-14 | 2019-08-23 | 中国舰船研究设计中心 | A kind of long timeliness secondary circuit passive residual heat removal system of water surface atomic-powered ship |
| CN113539530B (en) * | 2021-07-05 | 2022-12-09 | 西安交通大学 | Emergency heat exporting system of solid-state reactor core nuclear reactor for deep sea underwater navigation and working method |
| FR3131974A1 (en) * | 2022-01-19 | 2023-07-21 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Light water nuclear reactor (REL), in particular pressurized water (PWR) or boiling water (BWR), with cold source on the ground and integrating an autonomous residual heat removal system (EPUR). |
| FR3131973A1 (en) * | 2022-01-19 | 2023-07-21 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Light water nuclear reactor (LWR), in particular pressurized water (PWR) or boiling water (BWR), integrating a passive and autonomous residual heat removal system (EPUR). |
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