CN114758800A - Reactor core cooling method and system after emergency shutdown of high-temperature gas cooled reactor - Google Patents
Reactor core cooling method and system after emergency shutdown of high-temperature gas cooled reactor Download PDFInfo
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- CN114758800A CN114758800A CN202210535105.1A CN202210535105A CN114758800A CN 114758800 A CN114758800 A CN 114758800A CN 202210535105 A CN202210535105 A CN 202210535105A CN 114758800 A CN114758800 A CN 114758800A
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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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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F28—HEAT EXCHANGE IN GENERAL
- F28C—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA COME INTO DIRECT CONTACT WITHOUT CHEMICAL INTERACTION
- F28C1/00—Direct-contact trickle coolers, e.g. cooling towers
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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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
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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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
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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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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F28—HEAT EXCHANGE IN GENERAL
- F28C—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA COME INTO DIRECT CONTACT WITHOUT CHEMICAL INTERACTION
- F28C1/00—Direct-contact trickle coolers, e.g. cooling towers
- F28C2001/006—Systems comprising cooling towers, e.g. for recooling a cooling medium
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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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention provides a method and a system for cooling a reactor core after emergency shutdown of a high-temperature gas cooled reactor, wherein the cooling method comprises the following steps: helium is circulated between the reactor and the first circulation loop to transfer thermal energy of the reactor; the heat conducting oil circulates in the second circulation loop to transfer the heat energy of the helium gas; a heat exchanger is arranged between the first circulation loop and the second circulation loop, and the heat exchanger transfers the heat energy of the helium to the heat-conducting oil; the organic working medium circulates in the third circulation loop to transfer the heat energy of the heat conduction oil; an evaporator is arranged between the second circulation loop and the third circulation loop, the evaporator transfers heat energy of heat conduction oil to an organic working medium, and the organic working medium is heated and evaporated to form steam; and after doing work, the steam forms dead steam, and the dead steam is condensed and then circulated to the evaporator. The invention has the technical effects of reasonable design and improvement of the cooling efficiency of the reactor core.
Description
Technical Field
The invention belongs to the technical field of high-temperature gas cooled reactors, and particularly relates to a method and a system for cooling a reactor core of a high-temperature gas cooled reactor after emergency shutdown.
Background
When the high-temperature gas-cooled reactor is operated at full power and is in emergency shutdown, the main helium fan and the baffle are quickly closed, helium gas circulation cooling is lost in a primary circuit, the temperature of the reactor can be slowly raised and boosted under the action of waste heat, and the temperature of the reactor core is raised to above 1000 ℃ at most. The reactor can only be restarted after the core is cooled below a predetermined temperature (e.g., 200 ℃) and the temperature of the two-circuit feedwater is close.
The reactor core of the high-temperature gas cooled reactor comprises a large number of graphite fuel balls and graphite reactor internals, the heat storage capacity is large, a steam generator needs to be waited to finish cooling after emergency shutdown, the reactor core is cooled by a helium purification accident dehumidification column with small flow after the secondary side of the steam generator is filled with water, and the temperature of the reactor core can be reduced to the preset temperature within dozens of days. How to cool the reactor core in a short time and recover the grid-connected power generation of the unit as soon as possible is a technical problem which needs to be solved urgently in high-efficiency economic operation of the high-temperature gas cooled reactor.
Disclosure of Invention
The invention aims to at least solve one of the technical problems in the prior art and provides a novel technical scheme of a method and a system for cooling a reactor core after a high-temperature gas-cooled reactor is in emergency shutdown.
According to a first aspect of the invention, a core cooling method after a high temperature gas cooled reactor scram is provided, which comprises the following steps:
s101, circulating helium between a reactor and a first circulation loop to transfer heat energy of the reactor;
s102, circulating heat conducting oil in a second circulation loop to transfer heat energy of helium; a heat exchanger is arranged between the first circulation loop and the second circulation loop, and the heat exchanger transfers the heat energy of the helium to the heat-conducting oil;
s103, circulating the organic working medium in a third circulation loop to transfer heat energy of the heat conduction oil; an evaporator is arranged between the second circulation loop and the third circulation loop, the evaporator transfers the heat energy of the heat conduction oil to the organic working medium, and the organic working medium is heated and evaporated to form steam; and after the steam does work, dead steam is formed and is circulated to the evaporator after being condensed.
Optionally, the core cooling method after the high temperature gas cooled reactor emergency shutdown further comprises the following steps:
s104, circulating the liquid in a fourth circulation loop to transfer the heat energy of the dead steam; wherein the condenser is disposed between the third circulation loop and the fourth circulation loop, and the exhaust steam is condensed in the condenser and transfers heat energy to the liquid circulating in the fourth circulation loop.
Optionally, in step S103, the steam works to convert the heat energy into electric energy, and the electric energy is output to the power supply bus.
According to a second aspect of the present invention, there is provided a post-scram core cooling system for a high temperature gas cooled reactor, comprising:
a first circulation loop connected to the reactor, helium circulating between the reactor and the first circulation loop;
a second circulation circuit in which the conduction oil circulates;
the heat exchanger is arranged between the first circulation loop and the second circulation loop and used for transferring the heat energy of the helium to the heat conduction oil;
the organic working medium circulates in the third circulation loop;
the evaporator is arranged between the second circulation loop and the third circulation loop and used for transmitting heat energy of the heat conduction oil to the organic working medium, the organic working medium is heated and evaporated to form steam, the steam forms exhaust steam after acting, and the exhaust steam is condensed and then circulates to the evaporator.
Optionally, the high temperature gas cooled reactor post-scram core cooling system further includes:
a fourth circulation loop in which liquid circulates;
the condenser is arranged between the third circulation loop and the fourth circulation loop and is used for transferring the heat energy of the dead steam to liquid.
Optionally, the first circulation loop comprises a first circulation tube, an inlet isolation valve, an outlet isolation valve, a helium fan, and a helium flow regulator valve;
the first end and the second end of the first circulating pipe are respectively communicated with the reactor, and helium flows from the first end to the second end in the first circulating pipe;
an inlet isolation valve is arranged at the first end of the first circulation pipe, and an outlet isolation valve is arranged at the second end of the first circulation pipe;
the helium fan and the helium flow regulating valve are respectively arranged on the first circulating pipe, the helium fan is used for driving helium to circulate in the first circulating pipe, and the helium flow regulating valve is used for regulating the flow of the helium in the first circulating pipe.
Optionally, the second circulation loop comprises a second circulation pipe, a first circulation pump and a conduction oil flow regulating valve;
the two ends of the second circulating pipe are respectively connected with the heat exchanger, and the first circulating pump and the heat conduction oil flow regulating valve are respectively arranged on the second circulating pipe;
the first circulating pump is used for driving heat conduction oil to circulate in the second circulating pipe, and the heat conduction oil flow regulating valve is used for regulating the flow of the heat conduction oil in the second circulating pipe.
Optionally, the third circulation loop comprises a third circulation pipe, a turboset, and a second circulation pump;
the two ends of the third circulating pipe are respectively connected with the evaporator, and the steam turbine set and the second circulating pump are respectively arranged on the third circulating pipe;
the second circulating pump is used for driving the organic working medium to circulate in the third circulating pipe; the steam turbine set is used for converting the heat energy of the steam into electric energy.
Optionally, the fourth circulation loop comprises a fourth circulation pipe, a cooling water tower and a cooling water pump;
two ends of the fourth circulating pipe are respectively connected with the condenser, and the cooling water tower and the cooling water pump are respectively arranged on the fourth circulating pipe;
the cooling water pump is used for driving liquid to circulate in the fourth circulating pipe; the cooling tower is used for cooling liquid.
Optionally, the core cooling system after the high-temperature gas cooled reactor is in emergency shutdown further comprises a power supply bus, an emergency bus, a storage battery and a power supply line;
the steam turbine set is used for transferring the heat energy of the steam to electric energy and then transferring the electric energy to a power supply bus, and the power supply bus is respectively electrically connected with the emergency bus, the storage battery and the power supply line.
One technical effect of the invention is that:
in the application, after the high-temperature gas cooled reactor is in an emergency shutdown, the heat energy of the reactor core can be conveyed to the outside of the reactor core and quickly converted into other energy, such as electric energy, heat energy and the like, through the first circulation loop, the second circulation loop and the third circulation loop, the rapid cooling of the reactor core is realized, the cooling effect is good, and the working efficiency of the high-temperature gas cooled reactor is improved.
Drawings
FIG. 1 is a flow chart of a core cooling method after a high temperature gas cooled reactor scram according to an embodiment of the present invention;
fig. 2 is a schematic structural diagram of a core cooling system after an emergency shutdown of a high temperature gas cooled reactor according to an embodiment of the present invention.
In the figure: 100. a reactor; 200. a heat exchanger; 300. an evaporator; 400. a condenser; 11. a first circulation pipe; 12. an inlet isolation valve; 13. an outlet isolation valve; 14. a helium fan; 15. a helium flow regulating valve; 21. a second circulation pipe; 22. a first circulation pump; 23. a heat conducting oil flow regulating valve; 31. a third circulation pipe; 32. a steam turbine unit; 33. a second circulation pump; 41. a fourth circulation pipe; 42. a cooling water tower; 43. a cooling water pump; 5. a power supply bus; 6. an emergency bus; 7. a power supply line; 8. and (4) a storage battery.
Detailed Description
Various exemplary embodiments of the present application will now be described in detail with reference to the accompanying drawings. It should be noted that: the relative arrangement of the components and steps, the numerical expressions, and numerical values set forth in these embodiments do not limit the scope of the present application unless specifically stated otherwise.
Reference will now be made in detail to embodiments of the present application, examples of which are illustrated in the accompanying drawings, wherein like reference numerals refer to the same or similar elements or elements having the same or similar function throughout. The embodiments described below with reference to the accompanying drawings are illustrative and are only for the purpose of explaining the present application and are not to be construed as limiting the present application. All other embodiments obtained by a person of ordinary skill in the art based on the embodiments in the present application without making any creative effort belong to the protection scope of the present application.
The features of the terms first and second in the description and in the claims of the present application may explicitly or implicitly include one or more of those features. In the description of the present application, "a plurality" means two or more unless otherwise specified. In addition, "and/or" in the specification and claims means at least one of connected objects, a character "/" generally means that a preceding and succeeding related objects are in an "or" relationship.
In the description of the present application, it is to be understood that the terms "central," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," "circumferential," and the like are used in the orientations and positional relationships indicated in the drawings for convenience in describing the present application and to simplify the description, and are not intended to indicate or imply that the referenced devices or elements must have a particular orientation, be constructed and operated in a particular orientation, and are therefore not to be considered limiting of the present application.
In the description of the present application, it is to be noted that, unless otherwise explicitly specified or limited, the terms "mounted," "connected," and "connected" are to be construed broadly, e.g., as meaning either a fixed connection, a removable connection, or an integral connection; can be mechanically or electrically connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. The specific meaning of the above terms in this application will be understood to be a specific case for those of ordinary skill in the art.
Referring to fig. 1, according to a first aspect of the present invention, a method for cooling a reactor core after an emergency shutdown of a high temperature gas cooled reactor is provided, which is used for rapidly cooling the reactor core after the emergency shutdown, so as to reduce the temperature of the reactor core to a preset temperature in a short time, recover a unit of the high temperature gas cooled reactor to be grid-connected for power generation as soon as possible, and significantly improve the working efficiency of the high temperature gas cooled reactor.
Specifically, the method for cooling the reactor core after the emergency shutdown of the high-temperature gas cooled reactor comprises the following steps:
s101, helium is circulated between the reactor 100 and the first circulation loop to transfer heat energy of the reactor 100.
It should be noted that the first circulation loop is located outside the reactor 100, and the helium gas circulates between the reactor 100 and the first circulation loop, so that the thermal energy of the reactor 100 is rapidly output to the outside of the reactor 100, thereby effectively reducing the temperature of the core of the reactor 100.
S102, circulating heat conducting oil in a second circulation loop to transfer heat energy of helium; wherein a heat exchanger 200 is arranged between the first circulation loop and the second circulation loop, and the heat exchanger 200 transfers the heat energy of the helium gas to the heat-conducting oil.
In the second circulation loop, the heat conduction oil is used as a heat circulation medium, and the heat energy of the helium gas can be rapidly, stably and efficiently output to the evaporator 300, so that the transmission of the heat energy of the reactor 100 can be well completed, and the heat energy of the reactor 100 can be fully utilized.
S103, circulating the organic working medium in a third circulation loop to transfer heat energy of the heat conduction oil; an evaporator 300 is arranged between the second circulation loop and the third circulation loop, the evaporator 300 transfers the heat energy of the heat conduction oil to the organic working medium, and the organic working medium is heated and evaporated to form steam; the steam does work to form dead steam, and the dead steam is condensed and then circulated to the evaporator 300. The organic working medium circulates in the third circulation loop, so that heat energy can be better transferred, and the heat energy can be consumed conveniently by applying work through steam, thereby ensuring that the reactor 100 has a better cooling effect.
It should be noted that the evaporator 300 transfers the heat energy of the heat transfer oil to the organic working medium, and the organic working medium is heated and evaporated to form steam. By applying work to the steam, the heat energy of the reactor 100 is fully utilized, so that the reactor 100 can be rapidly cooled, and the working stability of the reactor 100 is ensured; and the heat energy of the reactor 100 can be quickly converted into other energy to realize the recycling of the energy, so that the energy can be better saved, the environment can be protected, and the cost can be effectively saved. For example, the work done by the steam may convert the heat energy of the steam into electrical energy, kinetic energy, and the like.
In the application, the method for cooling the reactor core after the high-temperature gas-cooled reactor is in emergency shutdown is reasonable in design. After the high-temperature gas cooled reactor is in emergency shutdown, the heat energy of the reactor core can be conveyed to the outside of the reactor core and quickly converted into other energy, such as electric energy, heat energy and the like, through the first circulation loop, the second circulation loop and the third circulation loop, the reactor core is quickly cooled, the cooling effect is good, and the working efficiency of the high-temperature gas cooled reactor is improved.
Optionally, the core cooling method after the high temperature gas cooled reactor emergency shutdown further comprises the following steps:
s104, circulating the liquid in a fourth circulation loop to transfer the heat energy of the dead steam; wherein the condenser 400 is provided between the third circulation loop and the fourth circulation loop, and the dead steam is condensed in the condenser 400 and transfers heat energy to the liquid circulating in the fourth circulation loop.
In the above embodiment, the liquid circulates in the fourth circulation loop, so that the thermal energy transfer efficiency of the reactor 100 can be further improved, the reactor 100 can be cooled quickly, and the cooling efficiency is improved.
And the liquid circulates in the fourth circulation loop, so that heat energy can be transferred to a plant water system and finally released to the environment, and the cooling efficiency of the reactor core is further improved. For example, the liquid may be water.
Alternatively, in step S103, the steam work converts the heat energy into electric energy, and outputs the electric energy to the power supply bus 5. The steam generator is not only beneficial to saving electric energy, but also has better stability and higher efficiency for converting heat energy into electric energy, and is beneficial to fully utilizing the heat energy of steam.
It is noted that the steam performs work in the steam turbine 32 and converts the heat energy into electrical energy.
The third circulation loop forms an ORC (organic working medium Rankine cycle) power generation module, the heat energy of the reactor core can be converted into electric energy, the power generation process is realized, and the heat energy utilization efficiency is high.
For example, the electric energy generated in the power generation process can supply power to the power utilization equipment in the reactor core cooling system and can also supply power to the emergency bus 6 in the plant area, thereby being beneficial to saving the electric energy.
Referring to fig. 2, according to a second aspect of the present invention, there is provided a post-scram core cooling system for a high temperature gas cooled reactor, comprising:
a first circulation loop connected to the reactor 100, helium gas circulating between the reactor 100 and the first circulation loop;
a second circulation circuit in which the conduction oil circulates;
the heat exchanger 200 is arranged between the first circulation loop and the second circulation loop and used for transferring the heat energy of the helium to the heat conduction oil;
the organic working medium circulates in the third circulation loop;
the evaporator 300 is arranged between the second circulation loop and the third circulation loop and used for transmitting heat energy of heat conduction oil to the organic working medium, the organic working medium is heated and evaporated to form steam, the steam forms exhaust steam after acting, and the exhaust steam is condensed and then circulates to the evaporator 300.
In the application, the reactor core cooling device after the high-temperature gas cooled reactor is in a reasonable design. After the high-temperature gas cooled reactor is in emergency shutdown, the heat energy of the reactor core can be conveyed to the outside of the reactor core and quickly converted into other energy, such as electric energy, heat energy and the like, through the first circulation loop, the second circulation loop and the third circulation loop, the reactor core is quickly cooled, the cooling effect is good, and the working efficiency of the high-temperature gas cooled reactor is improved.
Optionally, the high temperature gas cooled reactor post-scram core cooling system further includes:
a fourth circulation loop in which liquid circulates;
a condenser 400 disposed between the third circulation loop and the fourth circulation loop, the condenser 400 being used for transferring heat energy of the dead steam to the liquid.
In the above embodiment, the liquid circulates in the fourth circulation loop, so that the thermal energy transfer efficiency of the reactor 100 can be further improved, the reactor 100 can be cooled quickly, and the cooling efficiency is improved. Also, the exhaust steam is condensed in the condenser 400 and heat energy of the exhaust steam is efficiently transferred to the liquid to further improve the cooling efficiency of the core.
Optionally, the first circulation loop comprises a first circulation pipe 11, an inlet isolation valve 12, an outlet isolation valve 13, a helium fan 14 and a helium flow regulating valve 15;
the first end and the second end of the first circulation pipe 11 are respectively communicated with the reactor 100, and helium gas flows from the first end to the second end in the first circulation pipe 11;
an inlet isolation valve 12 is provided at a first end of the first circulation pipe 11 and an outlet isolation valve 13 is provided at a second end of the first circulation pipe 11;
a helium fan 14 and a helium flow regulating valve 15 are respectively arranged on the first circulation pipe 11, the helium fan 14 is used for driving helium to circulate in the first circulation pipe 11, and the helium flow regulating valve 15 is used for regulating the flow of helium in the first circulation pipe 11.
In the above embodiment, the first circulation circuit has a reasonable structural design, and helium gas can be rapidly circulated between the reactor 100 and the first circulation circuit, so that heat energy of the core can be rapidly transferred to the outside of the reactor 100, thereby improving the cooling efficiency of the reactor 100.
Optionally, the second circulation circuit comprises a second circulation pipe 21, a first circulation pump 22 and a thermal oil flow regulating valve 23;
both ends of the second circulation pipe 21 are respectively connected to the heat exchanger 200, and the first circulation pump 22 and the conduction oil flow control valve 23 are respectively disposed on the second circulation pipe 21;
the first circulation pump 22 is used for driving the conduction oil to circulate in the second circulation pipe 21, and the conduction oil flow regulating valve 23 is used for regulating the flow of the conduction oil in the second circulation pipe 21.
In the embodiment, the second circulation loop is reasonable in structural design, and the heat conduction oil can be rapidly circulated in the second circulation loop, so that the heat energy of the helium gas can be rapidly transferred to the heat conduction oil, and the transfer efficiency of the heat energy can be improved.
Optionally, the third circulation circuit comprises a third circulation pipe 31, a turboset 32, and a second circulation pump 33;
both ends of the third circulation pipe 31 are connected to the evaporator 300, respectively, and the turbine unit 32 and the second circulation pump 33 are disposed on the third circulation pipe 31, respectively;
the second circulation pump 33 is used for driving the organic working medium to circulate in the third circulation pipe 31; the steam turbine set 32 is configured to convert the heat energy of the steam into electrical energy.
In the above embodiment, the third circulation loop has a reasonable structural design, and can realize that the organic working medium can quickly circulate in the third circulation loop, so that the quick transmission of heat energy is realized, and the steam work can be realized, so that the heat energy is converted into electric energy, the utilization rate of the heat energy of the reactor core is improved, and the electric energy is saved.
Optionally, the fourth circulation loop comprises a fourth circulation pipe 41, a cooling water tower 42 and a cooling water pump 43;
both ends of the fourth circulation pipe 41 are respectively connected with the condenser 400, and the cooling water tower 42 and the cooling water pump 43 are respectively arranged on the fourth circulation pipe 41;
the cooling water pump 43 is used to drive the liquid circulation in the fourth circulation pipe 41; the cooling water tower 42 is used to cool the liquid.
In the above embodiment, the liquid circulates in the fourth circulation loop, so that the thermal energy transfer efficiency of the reactor 100 can be further improved, the reactor 100 can be cooled quickly, and the cooling efficiency is improved.
Optionally, the core cooling system after the high temperature gas cooled reactor is in emergency shutdown further comprises a power supply bus 5, an emergency bus 6, a storage battery 8 and a power supply line 7;
after the steam turbine set 32 is used for converting the heat energy of steam into electric energy, the electric energy is transmitted to the power supply bus 5, and the power supply bus 5 is respectively electrically connected with the emergency bus 6, the storage battery 8 and the power supply line 7.
In the above embodiment, the power supply bus 5 is electrically connected to the emergency bus 6, the storage battery 8, and the power supply line 7, respectively, and therefore, the electric energy converted from the core thermal energy can be supplied to both the emergency bus 6 and the storage battery 8, and also to the power supply line 7, and the electric energy can be sufficiently used.
It should be noted that the emergency bus 6 (the emergency bus 6 is the plant emergency bus 6), the storage battery 8, and the power supply line 7 are electrically connected to the power supply bus 5, wherein the power supply line 7 is used for supplying power to the helium fan 14, the first circulation pump 22, the second circulation pump 33, the cooling water pump 43, and other rotating devices in the cooling system.
In the first state, namely under the working condition that the electric energy of the high-temperature gas cooled reactor is stably supplied, at the moment, the emergency bus 6 is not de-energized, the emergency bus 6 can supply power to the power supply bus 5, and the emergency bus 6 can also supply power to the power supply line 7, so that the reactor core cooling system can be started. The power supply bus 5 is electrically connected with the storage battery 8, so that the storage battery 8 is in a floating charging state, and the storage battery 8 is favorably protected and is in a full-charge state.
Under the second state, under the station blackout accident condition, the emergency bus 6 loses power, the storage battery 8 supplies power to the rotating equipment in the reactor core cooling system, the reactor core cooling system is started, and after the reactor core cooling system is started, the power can be supplied to the emergency bus 6 besides the power supplied to the rotating equipment in the system, so that the availability of important equipment of the nuclear power plant under the accident condition is improved.
After the reactor 100 is brought into an emergency shutdown, the operator quickly analyzes the reason of the shutdown to prepare for starting the core cooling system, and if the emergency bus 6 is not powered off, the electrical equipment in the core cooling system can be started through the emergency bus 6, and if the emergency bus 6 is powered off, the electrical equipment in the core cooling system can be started through the storage battery 8. The specific operation is as follows:
first, the inlet isolation valve 12 and the outlet isolation valve 13 are opened, the helium fan 14 is started, and the first circulation pump 22 is started. Helium in the reactor 100 enters the heat exchanger 200 under the driving of the helium fan 14, and heat energy is transferred to the heat conducting oil. The opening degree of the helium flow regulating valve 15 is adjusted to regulate the flow of the helium gas entering the heat exchanger 200, and the heat transfer oil is gradually heated to 300 ℃.
Then, the cooling water pump 43 and the second circulation pump 33 are started during the heating process, and the conduction oil is driven by the first circulation pump 22 to enter the evaporator 300. The opening degree of the heat transfer oil flow rate control valve 23 is adjusted to adjust the flow rate of the heat transfer oil entering the evaporator 300.
Then, the organic working medium in the evaporator 300 is heated into steam, the steam enters the steam turbine set 32 to generate electricity, and the exhaust steam after doing work enters the condenser 400 and is cooled into liquid state by the liquid (such as factory water) driven by the cooling water pump 43.
Subsequently, the liquid organic working medium enters the evaporator 300 to form a circulation under the driving of the second circulation pump 33.
Finally, the steam turbine set 32 generates power and supplies the power to the power supply bus 5, and the power is used for supplying power to the rotating equipment (such as the helium fan 14, the first circulating pump 22, the second circulating pump 33, the cooling water pump 43 and the like) in the core cooling system in the initial stage, and as the load increases, redundant power can be supplied to the emergency bus 6 for power utilization of other equipment in the plant area. This not only effectively recovers the heat of the reactor 100, but also has significant economic benefits.
In addition, under the emergency condition of power loss of the whole plant, the power supply can be used for supplying power to the safety level equipment of the power plant, and the usability of the safety equipment of the nuclear power plant is improved.
In the embodiment of the application, the method and the system for cooling the reactor core after the high-temperature gas cooled reactor is in emergency shutdown have the following advantages:
firstly, the heat energy of the reactor core is converted into electric energy, meanwhile, partial heat energy is taken away through a plant water system and released to the environment, and compared with the original natural circulation heat dissipation and cooling of a power plant, the cooling capacity is greatly enhanced. For example, in specific practice, the cooling time of the reactor core can be shortened from more than ten days to two to three days, so that the unit grid-connected power generation of the high-temperature gas-cooled reactor can be recovered as soon as possible, the working efficiency of the high-temperature gas-cooled reactor is remarkably improved, and the economic benefit is remarkable.
Secondly, under the condition that the high-temperature gas cooled reactor has a power outage accident of the whole plant, on one hand, the reactor core can be rapidly cooled, on the other hand, the heat energy of the reactor core is converted into electric energy in the cooling process, and the electric energy can be supplied to the emergency bus 6 of the power plant, so that the availability of safety level equipment of the power plant under the accident condition is ensured.
Thirdly, the reactor core cooling system can be started by using the storage battery 8, and the reactor core cooling system is self-powered after being started and operated, does not depend on an external power supply, and further improves the safety.
Fourthly, the heat energy of the helium gas with high temperature and high pressure in the reactor core is transferred to a third circulation loop through the heat transfer oil in the second circulation loop, the third circulation loop can be an ORC power generation module, the heat transfer oil is not vaporized under the condition of 300 ℃ and keeps normal pressure, therefore, a low-pressure pipeline can be used for the second circulation pipe 21, a low-power pump can be used for the first circulation pump 22, and the investment is low. In addition, the heat conduction oil has the characteristics of uniform heat transfer, good thermal stability and excellent heat conduction, so that the heat energy of the helium can be quickly transferred to the organic medium, and the heat conduction oil is favorable for the evaporation of the organic medium to form steam to do work.
Fifthly, the heat conducting oil has no corrosion effect on common carbon steel equipment and pipelines, so that the core cooling system after the high-temperature gas-cooled reactor is in emergency shutdown is simpler and more reliable.
Sixthly, the third circulation loop, namely the ORC power supply module, has the advantages of compact structure, small occupied area, easiness in field arrangement, flexibility in load change and simplicity in operation and maintenance, and meanwhile, the Rankine cycle efficiency of the organic working medium is higher than that of water serving as the working medium, and the main reason is that the ORC has higher efficiency in the aspect of sensible heat recovery, so that more heat energy can be recovered by adopting the ORC technology for power generation, the heat energy of a reactor core is fully utilized, and the usability of nuclear power plant equipment under the accident condition is remarkably improved.
Seventh, after the high temperature reactor gas cooled reactor is in emergency shutdown, the reactor core temperature is over 1000 ℃, compared with the coolant temperature of a pressurized water reactor primary loop of about 300 ℃, the recycling value is higher, the effect is better, the organic working medium can generate warm steam and generate electricity under rated power for a long time, and the generating efficiency is high.
Eighthly, the reactor core is cooled by four circulation loops which are isolated from each other, so that the risk of radioactive leakage is reduced, and heat energy of high-temperature and high-pressure helium gas is transferred to high-temperature and normal-pressure heat conduction oil, so that heat energy can be conveniently led out and generated, the control is easy, and the safety is high.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.
Claims (10)
1. A method for cooling a reactor core after a high-temperature gas cooled reactor is subjected to emergency shutdown is characterized by comprising the following steps:
s101, helium circulates between a reactor and a first circulation loop to transfer heat energy of the reactor;
s102, circulating heat conducting oil in a second circulation loop to transfer heat energy of helium; a heat exchanger is arranged between the first circulation loop and the second circulation loop, and the heat exchanger transfers the heat energy of the helium to the heat-conducting oil;
s103, circulating the organic working medium in a third circulation loop to transfer heat energy of the heat conduction oil; an evaporator is arranged between the second circulation loop and the third circulation loop, the evaporator transfers the heat energy of the heat conduction oil to the organic working medium, and the organic working medium is heated and evaporated to form steam; and after the steam does work, dead steam is formed and is circulated to the evaporator after being condensed.
2. The method for cooling the reactor core after the emergency shutdown of the high temperature gas cooled reactor according to claim 1, further comprising the steps of:
s104, circulating the liquid in a fourth circulation loop to transfer the heat energy of the dead steam; wherein the condenser is disposed between the third circulation loop and the fourth circulation loop, and the dead steam is condensed in the condenser and transfers heat energy to the liquid circulating in the fourth circulation loop.
3. The method for cooling the core after the scram of the high temperature gas cooled reactor according to claim 1,
in step S103, the steam works to convert the heat energy into electric energy, and the electric energy is output to the power supply bus.
4. A core cooling system after emergency shutdown of a high temperature gas cooled reactor, comprising:
a first circulation loop connected to the reactor, helium circulating between the reactor and the first circulation loop;
a second circulation circuit in which the conduction oil circulates;
the heat exchanger is arranged between the first circulation loop and the second circulation loop and used for transferring the heat energy of the helium to the heat conduction oil;
the organic working medium circulates in the third circulation loop;
the evaporator is arranged between the second circulation loop and the third circulation loop and used for transmitting heat energy of the heat conduction oil to the organic working medium, the organic working medium is heated and evaporated to form steam, the steam forms exhaust steam after acting, and the exhaust steam is condensed and then circulates to the evaporator.
5. The system of claim 4, further comprising:
a fourth circulation loop in which liquid circulates;
the condenser is arranged between the third circulation loop and the fourth circulation loop and is used for transferring the heat energy of the dead steam to liquid.
6. The post-scram core cooling system of claim 5, wherein the first circulation loop comprises a first circulation pipe, an inlet isolation valve, an outlet isolation valve, a helium fan and a helium flow regulating valve;
the first end and the second end of the first circulating pipe are respectively communicated with the reactor, and helium flows from the first end to the second end in the first circulating pipe;
an inlet isolation valve is arranged at the first end of the first circulation pipe, and an outlet isolation valve is arranged at the second end of the first circulation pipe;
the helium fan and the helium flow regulating valve are respectively arranged on the first circulating pipe, the helium fan is used for driving helium to circulate in the first circulating pipe, and the helium flow regulating valve is used for regulating the flow of the helium in the first circulating pipe.
7. The reactor core cooling system after the emergency shutdown of the high temperature gas cooled reactor of claim 5, wherein the second circulation loop comprises a second circulation pipe, a first circulation pump and a heat transfer oil flow regulating valve;
the two ends of the second circulating pipe are respectively connected with the heat exchanger, and the first circulating pump and the heat conduction oil flow regulating valve are respectively arranged on the second circulating pipe;
the first circulating pump is used for driving heat conduction oil to circulate in the second circulating pipe, and the heat conduction oil flow regulating valve is used for regulating the flow of the heat conduction oil in the second circulating pipe.
8. The high temperature gas cooled reactor post scram core cooling system of claim 5, wherein the third circulation loop comprises a third circulation pipe, a steam turbine set, and a second circulation pump;
the two ends of the third circulating pipe are respectively connected with the evaporator, and the steam turbine set and the second circulating pump are respectively arranged on the third circulating pipe;
the second circulating pump is used for driving the organic working medium to circulate in the third circulating pipe; the steam turbine set is used for converting heat energy of steam into electric energy.
9. The post-scram core cooling system of the high temperature gas cooled reactor of claim 8, wherein the fourth circulation loop comprises a fourth circulation pipe, a cooling water tower and a cooling water pump;
two ends of the fourth circulating pipe are respectively connected with the condenser, and the cooling water tower and the cooling water pump are respectively arranged on the fourth circulating pipe;
the cooling water pump is used for driving liquid to circulate in the fourth circulating pipe; the cooling tower is used for cooling liquid.
10. The high temperature gas cooled reactor post scram core cooling system of claim 8, further comprising a power supply bus, an emergency bus, a storage battery and a power supply line;
after the steam turbine set is used for converting the heat energy of steam into electric energy, the electric energy is transmitted to a power supply bus, and the power supply bus is respectively electrically connected with the emergency bus, the storage battery and the power supply line.
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