CN114758800B

CN114758800B - Method and system for cooling reactor core after emergency shutdown of high-temperature gas cooled reactor

Info

Publication number: CN114758800B
Application number: CN202210535105.1A
Authority: CN
Inventors: 黄鹏; 赵峰; 彭帅; 徐校飞; 王锐
Original assignee: Huaneng Shandong Shidaobay Nuclear Power Co Ltd
Current assignee: Huaneng Shandong Shidaobay Nuclear Power Co Ltd
Priority date: 2022-05-17
Filing date: 2022-05-17
Publication date: 2023-05-12
Anticipated expiration: 2042-05-17
Also published as: CN114758800A

Abstract

The invention provides a cooling method and a cooling system for a reactor core after emergency shutdown of a high-temperature gas cooled reactor, wherein the cooling method comprises the following steps: helium circulates between the reactor and the first circulation loop to transfer thermal energy from the reactor; the heat conducting oil circulates in the 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 heat energy of helium to heat conduction oil; the organic working medium circulates in the third circulation loop to transfer the heat energy of the heat conducting 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 the steam forms exhaust steam after acting, and the exhaust steam is condensed and then is circulated to the evaporator. The invention has the technical effect that the design is reasonable, and the cooling efficiency of the reactor core is improved.

Description

Method and system for cooling reactor core after emergency shutdown of high-temperature gas cooled reactor

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 after emergency shutdown of a high-temperature gas cooled reactor.

Background

When the high-temperature gas cooled reactor is in emergency shutdown in full-power operation, the main helium fan and the baffle plate are quickly closed, the primary loop loses helium circulation cooling, the reactor can slowly heat up and boost pressure under the action of waste heat, and the temperature of the reactor core is up to more than 1000 ℃. The reactor can be restarted only after the core is cooled below a predetermined temperature (e.g., 200 ℃) and is close to the secondary feedwater temperature.

The high-temperature gas cooled reactor core comprises a large number of graphite fuel balls and graphite reactor internals, the heat accumulation amount is large, the steam generator needs to wait for cooling after emergency shutdown, the reactor core is cooled by means of helium purification accident dehumidification column low flow after the secondary side of the steam generator is supplied with water, and the temperature of the reactor core can be reduced to a preset temperature only in ten 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 becomes a technical problem to be solved in high-efficiency and economical operation of the high-temperature gas cooled reactor.

Disclosure of Invention

The invention aims at solving at least one of the technical problems existing in the prior art and provides a novel technical scheme of a method and a system for cooling a reactor core after emergency shutdown of a high-temperature gas cooled reactor.

According to a first aspect of the invention, there is provided a method for cooling a post-emergency shutdown reactor core of a high temperature gas cooled reactor, comprising the steps of:

s101, helium circulates between the reactor and the first circulation loop to transfer heat energy of the reactor;

s102, circulating heat conduction 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 heat energy of helium to heat conduction oil;

s103, circulating the organic working medium in a third circulation loop to transfer heat energy of the heat conducting 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 the steam forms exhaust steam after acting, and the exhaust steam is condensed and then is circulated to the evaporator.

Optionally, the method for cooling the reactor core after the emergency shutdown of the high-temperature gas cooled reactor further comprises the following steps:

s104, circulating the liquid in a fourth circulation loop to transfer the heat energy of the exhaust steam; the condenser is arranged between the third circulation loop and the fourth circulation loop, and exhaust steam is condensed in the condenser and transfers heat energy to liquid circulating in the fourth circulation loop.

Optionally, in step S103, the steam performs work to convert thermal energy into electrical energy and outputs the electrical energy to the power 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 heat transfer oil circulates;

a heat exchanger arranged between the first circulation loop and the second circulation loop and used for transferring heat energy of helium to heat conduction oil;

a third circulation circuit in which the organic working medium circulates;

and the evaporator is arranged between the second circulation loop and the third circulation loop and is used for transferring the 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 circulated to the evaporator.

Optionally, the post-emergency shutdown reactor core cooling system of the high-temperature gas cooled reactor further comprises:

a fourth circulation circuit in which a liquid circulates;

and 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 the liquid.

Optionally, the first circulation loop comprises a first circulation pipe, an inlet isolation valve, an outlet isolation valve, a helium blower, 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 gas flows from the first end to the second end in the first circulating pipe;

the inlet isolation valve is arranged at the first end of the first circulating pipe, and the outlet isolation valve is arranged at the second end of the first circulating pipe;

the helium blower and the helium flow regulating valve are respectively arranged on the first circulating pipe, the helium blower 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 conducting oil flow regulating valve are respectively arranged on the second circulating pipe;

the first circulating pump is used for driving the 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 turbine set, and a second circulation pump;

the two ends of the third circulating pipe are respectively connected with the evaporator, and the turbine unit 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 unit is used for converting heat energy of steam into electric energy.

Optionally, the fourth circulation loop comprises a fourth circulation pipe, a cooling water tower and a cooling water pump;

the 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 water tower is used for cooling liquid.

Optionally, the high-temperature gas cooled reactor emergency shutdown post-reactor core cooling system further comprises a power supply bus, an emergency bus, a storage battery and a power supply line;

after the steam turbine unit is used for converting heat energy of steam into electric energy, the electric energy is transmitted to a power supply bus, and the power supply bus is respectively and electrically connected with the emergency bus, the storage battery and the power supply line.

The invention has the technical effects that:

in this application, high temperature gas cooled reactor is in the emergency shutdown after, through first circulation loop, second circulation loop and third circulation loop, can carry the outside of reactor core heat energy to the reactor core and convert into other energy rapidly, for example electric energy, heat energy etc. to realize the quick cooling to the reactor core, and the cooling effect is better, has improved high temperature gas cooled reactor's work efficiency.

Drawings

FIG. 1 is a flow chart of a method for cooling a post-emergency shutdown reactor core of a high temperature gas cooled reactor in accordance with an embodiment of the present invention;

FIG. 2 is a schematic diagram of a post-emergency shutdown reactor core cooling system for a high temperature gas cooled reactor according to an embodiment of the 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 blower; 15. a helium flow regulating valve; 21. a second circulation pipe; 22. a first circulation pump; 23. a conduction oil flow regulating valve; 31. a third circulation pipe; 32. a 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 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, numerical expressions and numerical values set forth in these embodiments do not limit the scope of the present application unless it is 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 or similar reference numerals refer to like or similar elements or elements having like or similar functionality throughout. The embodiments described below by referring to the drawings are exemplary only for the purpose of explaining the present application and are not to be construed as limiting the present application. All other embodiments, which can be made by one of ordinary skill in the art based on the embodiments herein without making any inventive effort, are intended to be within the scope of the present application.

The features of the terms "first", "second", and the like in the description and in the claims of this application may be used for descriptive or implicit inclusion of one or more such features. In the description of the present application, unless otherwise indicated, the meaning of "a plurality" is two or more. Furthermore, in the description and claims, "and/or" means at least one of the connected objects, and the character "/", generally means that the associated object is an "or" relationship.

In the description of the present application, it should be understood that the terms "center," "longitudinal," "transverse," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," "circumferential," etc. indicate orientations or positional relationships based on the orientations or positional relationships illustrated in the drawings, are merely for convenience in describing the present application and simplifying the description, and do not indicate or imply that the device or element being referred to must have a particular orientation, be configured and operated in a particular orientation, and therefore should not be construed as limiting the present application.

In the description of the present application, it should be noted that, unless explicitly specified and limited otherwise, the terms "mounted," "connected," and "connected" are to be construed broadly, and may be either fixedly connected, detachably connected, or integrally connected, for example; 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 terms in this application will be understood by those of ordinary skill in the art in a specific context.

Referring to fig. 1, according to a first aspect of the present invention, a post-emergency shutdown reactor core cooling method for a high-temperature gas cooled reactor is provided, which is used for rapidly cooling a reactor core after emergency shutdown, so as to reduce the temperature of the reactor core to a preset temperature in a short time, recover unit grid-connected power generation of the high-temperature gas cooled reactor 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 circulates between the reactor 100 and the first circulation loop to transfer thermal energy of the reactor 100.

It should be noted that the first circulation loop is located outside the reactor 100, and the helium circulates between the reactor 100 and the first circulation loop, so that the heat energy of the reactor 100 is rapidly output to the outside of the reactor 100, so as to effectively reduce the temperature of the core of the reactor 100.

S102, circulating heat conduction oil in a second circulation loop to transfer heat energy of helium; wherein a heat exchanger 200 is provided between the first and second circulation loops, the heat exchanger 200 transferring heat energy of helium gas to the heat transfer oil.

In the second circulation loop, the heat conducting oil is used as a heat circulation medium, so that the heat energy of the helium can be quickly, stably and efficiently output to the evaporator 300, thereby better completing the transmission of the heat energy of the reactor 100 and being beneficial to fully utilizing the heat energy of the reactor 100.

S103, circulating the organic working medium in a third circulation loop to transfer heat energy of the heat conducting 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 an organic working medium, and 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 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 conveniently consumed by acting through steam, thereby ensuring that the reactor 100 has a better cooling effect.

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. By making the steam do work to fully utilize the heat energy of the reactor 100, not only can the reactor 100 be rapidly cooled, but also the working stability of the reactor 100 can be ensured; and the heat energy of the reactor 100 can be rapidly converted into other energy to realize the recycling of the energy, thereby saving the energy better, protecting the environment and saving the cost effectively. For example, the steam may perform work to convert thermal energy of the steam into electrical energy, kinetic energy, and the like.

In the application, the cooling method of the reactor core after the emergency shutdown of the high-temperature gas cooled reactor is reasonable in design. After the high-temperature gas cooled reactor is in emergency shutdown, heat energy of the reactor core can be conveyed to the outside of the reactor core through the first circulation loop, the second circulation loop and the third circulation loop and is rapidly converted into other energy such as electric energy, heat energy and the like, so that the reactor core is rapidly cooled, the cooling effect is good, and the working efficiency of the high-temperature gas cooled reactor is improved.

s104, circulating the liquid in a fourth circulation loop to transfer the heat energy of the exhaust steam; wherein the condenser 400 is provided between the third circulation loop and the fourth circulation loop, and exhaust 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 heat energy transfer efficiency of the reactor 100 can be further improved by circulating the liquid in the fourth circulation loop, which is advantageous for rapidly cooling the reactor 100 and improves the cooling efficiency.

The liquid circulates in the fourth circulation loop, so that heat energy can be transferred to the water system of the plant and finally released to the environment, and the cooling efficiency of the reactor core can be further improved. For example, the liquid may be water.

Optionally, in step S103, the steam performs work to convert thermal energy into electrical energy and output the electrical energy to the power supply bus 5. Not only is favorable for saving electric energy, but also the stability of converting heat energy into electric energy is better, the efficiency is higher, and the heat energy of the steam is favorable for fully utilizing.

The steam performs work in the turbine unit 32 and converts thermal energy into electric energy.

The third circulation loop forms an ORC (organic working medium Rankine cycle) power generation module, can convert heat energy of the reactor core into electric energy and realize a power generation process, and has higher heat energy utilization efficiency.

For example, the electric energy generated in the power generation process can supply power to the emergency bus 6 in the factory besides supplying power to electric equipment in the reactor core cooling system, so that the electric energy can be saved.

Referring to FIG. 2, in accordance with 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 heat transfer oil circulates;

a heat exchanger 200, wherein the heat exchanger 200 is arranged between the first circulation loop and the second circulation loop and is used for transferring heat energy of helium gas to heat conduction oil;

a third circulation circuit in which the organic working medium circulates;

and the evaporator 300 is arranged between the second circulation loop and the third circulation loop, and is used for transferring the heat energy of the heat conducting oil to an organic working medium, the organic working medium is heated and evaporated to form steam, and the steam forms exhaust steam after acting, and the exhaust steam is condensed and then circulated to the evaporator 300.

In the application, the reactor core cooling device after the emergency shutdown of the high-temperature gas cooled reactor is reasonable in design. After the high-temperature gas cooled reactor is in emergency shutdown, heat energy of the reactor core can be conveyed to the outside of the reactor core through the first circulation loop, the second circulation loop and the third circulation loop and is rapidly converted into other energy such as electric energy, heat energy and the like, so that the reactor core is rapidly cooled, the cooling effect is good, and the working efficiency of the high-temperature gas cooled reactor is improved.

a fourth circulation circuit in which a liquid circulates;

and a condenser 400 arranged between the third circulation loop and the fourth circulation loop, wherein the condenser 400 is used for transferring the heat energy of the dead steam to the liquid.

In the above embodiment, the heat energy transfer efficiency of the reactor 100 can be further improved by circulating the liquid in the fourth circulation loop, which is advantageous for rapidly cooling the reactor 100 and improves the cooling efficiency. 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 includes a first circulation pipe 11, an inlet isolation valve 12, an outlet isolation valve 13, a helium blower 14, and a helium flow regulating valve 15;

the first and second ends 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 blower 14 and a helium flow regulating valve 15 are respectively provided in the first circulation pipe 11, the helium blower 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 loop has a reasonable structural design, and can realize rapid circulation of helium between the reactor 100 and the first circulation loop, thereby rapidly transferring heat energy of the core to the outside of the reactor 100, so as to improve cooling efficiency of the reactor 100.

Optionally, the second circulation loop includes a second circulation pipe 21, a first circulation pump 22, and a conduction oil flow rate adjustment valve 23;

two ends of the second circulation pipe 21 are respectively connected with the heat exchanger 200, and the first circulation pump 22 and the heat transfer oil flow regulating valve 23 are respectively arranged on the second circulation pipe 21;

the first circulation pump 22 is used for driving the heat transfer oil to circulate in the second circulation pipe 21, and the heat transfer oil flow rate regulating valve 23 is used for regulating the flow rate of the heat transfer oil in the second circulation pipe 21.

In the above embodiment, the structural design of the second circulation loop is reasonable, and the heat conduction oil can be rapidly circulated in the second circulation loop, so that the heat energy of helium can be rapidly transferred to the heat conduction oil, and the heat energy transfer efficiency is improved.

Optionally, the third circulation loop includes a third circulation pipe 31, a steam turbine unit 32, and a second circulation pump 33;

the two ends of the third circulation pipe 31 are respectively connected with the evaporator 300, and the steam turbine unit 32 and the second circulation pump 33 are respectively arranged on the third circulation pipe 31;

the second circulation pump 33 is used for driving the organic working medium to circulate in the third circulation pipe 31; the steam turbine unit 32 is configured to convert thermal energy of steam into electrical energy.

In the embodiment, the third circulation loop has reasonable structural design, and can realize the rapid circulation of the organic working medium in the third circulation loop, thereby realizing the rapid transmission of heat energy and the acting of steam, further converting the heat energy into electric energy, improving the utilization rate of the heat energy of the reactor core and being beneficial to saving the electric energy.

Alternatively, the fourth circulation loop includes 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 for driving the liquid to circulate in the fourth circulation pipe 41; the cooling tower 42 is used for cooling the liquid.

Optionally, the high-temperature gas cooled reactor emergency shutdown post-reactor core cooling system 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 unit 32 is configured to convert thermal energy of steam into electrical energy, the electrical energy is transmitted to the power supply bus 5, and the power supply bus 5 is electrically connected to the emergency bus 6, the storage battery 8, and the power supply line 7, respectively.

In the above embodiment, the power supply bus 5 is electrically connected to the emergency bus 6, the battery 8, and the power supply line 7, respectively, and therefore, the electric energy converted by the core heat energy can be supplied to both the emergency bus 6 and the battery 8, and also to the power supply line 7, thereby making full use of the electric energy.

The emergency bus bar 6 (the emergency bus bar 6 is a factory area emergency bus bar 6), the storage battery 8, and the power supply line 7 are electrically connected to the power supply bus bar 5, wherein the power supply line 7 is used for supplying power to rotating equipment such as the helium blower 14, the first circulation pump 22, the second circulation pump 33, the cooling water pump 43, and the like in the cooling system.

In the first state, namely under the working condition that the electric energy supply of the high-temperature gas cooled reactor is stable, the emergency bus 6 is not powered off, 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 for realizing the starting of the reactor core cooling system. The power supply bus 5 is electrically connected with the storage battery 8, so that the storage battery 8 is in a floating charge state, and the storage battery 8 is better protected and is in a full-charge state.

In the second state, under the whole plant power failure accident working condition, the emergency bus 6 is powered off, the storage battery 8 supplies power to rotating equipment in the reactor core cooling system and is used for starting the reactor core cooling system, the power supply to the rotating equipment in the system can be further used for supplying power to the emergency bus 6 after the reactor core cooling system is started, and the availability of important equipment of the nuclear power plant under the accident condition is improved.

After the reactor 100 is suddenly shut down, an operator rapidly analyzes the reason for the shutdown, and prepares to start the core cooling system, if the emergency bus 6 is not powered down at this time, the electric equipment in the core cooling system can be started through the emergency bus 6, and if the emergency bus 6 is powered down, the electric 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 blower 14 is started, and the first circulation pump 22 is started. Helium gas in the reactor 100 enters the heat exchanger 200 under the drive of the helium blower 14 to transfer heat energy to the heat transfer oil. The opening degree of the helium flow regulating valve 15 was adjusted to adjust the flow rate of helium gas entering the heat exchanger 200, and the heat transfer oil was gradually heated to 300 ℃.

Then, the cooling water pump 43 and the second circulation pump 33 are started during the heating process, and the heat transfer oil is introduced into the evaporator 300 by the driving of the first circulation pump 22. The opening degree of the conduction oil flow rate adjusting valve 23 is adjusted to adjust the conduction oil flow rate into the evaporator 300.

Then, the organic working medium in the evaporator 300 is heated to steam, the steam enters the turbine unit 32 to generate electricity, and the exhaust steam after the work enters the condenser 400 to be cooled to liquid state by liquid (for example, water for a factory) driven by the cooling water pump 43.

Subsequently, the liquid organic working medium is driven by the second circulation pump 33 to enter the evaporator 300 to form a circulation.

Finally, the turbine unit 32 generates electricity and supplies it to the power supply bus 5, which is initially used for power supply to the rotating equipment (e.g., helium fan 14, first circulation pump 22, second circulation pump 33, cooling water pump 43, etc.) in the core cooling system, and as the load increases, excess power can be supplied to the emergency bus 6 for power utilization by other equipment in the plant. This not only effectively recovers the heat of the reactor 100, but also has remarkable economic benefits.

In addition, in the emergency of power failure of the whole plant, power can be supplied to the safety equipment of the power plant, and the availability 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 emergency shutdown post-reactor core of the high-temperature gas cooled reactor have the following advantages:

firstly, the heat energy of the reactor core is converted into electric energy, and meanwhile, part of heat energy is taken away through a water system of a plant and released into the environment, so that 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 obviously improved, and the economic benefit is obvious.

Secondly, under the condition that the whole plant power failure accident occurs in the high-temperature gas cooled reactor, 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 usability of safety 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 is self-powered after being started and operated, and the safety is further improved without depending on an external power supply.

Fourth, the heat energy of the helium gas with high temperature and high pressure in the reactor core is transferred to the third circulation loop through the heat conduction oil in the second circulation loop, the third circulation loop can be an ORC power generation module, the heat conduction oil is still not vaporized under the condition of 300 ℃ and is kept at normal pressure, therefore, the second circulation loop 21 can use a low-pressure pipeline, the first circulation pump 22 can use a low-power pump, and the investment is low. In addition, the heat conducting oil also has the advantages of uniform heat transfer, good heat stability and excellent heat conducting property, so that the heat energy of helium can be quickly transferred to an organic medium, and the evaporation of the organic medium to form steam to do work is facilitated.

Fifth, the conduction oil has no corrosion effect on common carbon steel equipment and pipelines, so the reactor core cooling system after the emergency shutdown of the high-temperature gas cooled reactor is simpler and more reliable.

Sixth, the third circulation loop, namely the ORC power supply module, is compact in structure, small in occupied area, easy to arrange in site, flexible in load change, simple to operate and maintain, and meanwhile, the efficiency of the organic working medium Rankine cycle is higher than that of the Rankine cycle taking water as a working medium, and the main reason is that ORC has higher efficiency in the aspect of sensible heat recovery, so that more heat energy can be recovered for power generation by adopting an ORC technology, 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 up to more than 1000 ℃, and compared with the temperature of a pressurized water reactor primary loop coolant, the recovery 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 electricity generation efficiency is high.

Eighth, use four circulation loops of mutual isolation to cool down the reactor core, reduced the risk that radioactivity leaked, with the heat energy transfer of high temperature high pressure helium for high temperature normal pressure conduction oil to the derivation of heat energy and electricity generation, easily control, the security is high.

It is to be understood that the above embodiments are merely illustrative of the application of the principles of the present invention, but not in limitation thereof. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the invention, and are also considered to be within the scope of the invention.

Claims

1. The cooling method of the emergency shutdown post-reactor core of the high-temperature gas cooled reactor is characterized by comprising the following steps of:

s103, circulating the organic working medium in a third circulation loop to transfer heat energy of the heat conducting 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; the steam forms exhaust steam after acting, and the exhaust steam is condensed and then circulated to the evaporator; in step S103, the steam does work to convert thermal energy into electric energy, and outputs the electric energy to the power supply bus;

s104, circulating the liquid in a fourth circulation loop to transfer the heat energy of the exhaust steam; and a condenser is arranged between the third circulation loop and the fourth circulation loop, and exhaust steam is condensed in the condenser and transfers heat energy to liquid circulating in the fourth circulation loop.

2. A high temperature gas cooled reactor scram post core cooling system, comprising:

a second circulation circuit in which the heat transfer oil circulates;

a third circulation circuit in which the organic working medium circulates;

the evaporator is arranged between the second circulation loop and the third circulation loop and is used for transferring the heat energy of the heat conducting 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 circulated to the evaporator;

a fourth circulation circuit in which a liquid circulates;

3. The high temperature gas cooled reactor scram post core cooling system as set forth in claim 2, wherein said 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;

4. The high temperature gas cooled reactor scram post core cooling system as set forth in claim 2 wherein said second circulation loop comprises a second circulation tube, a first circulation pump and a heat transfer oil flow regulator valve;

5. The high temperature gas cooled reactor scram post core cooling system as set forth in claim 2, wherein said third circulation loop comprises a third circulation pipe, a turbine unit, and a second circulation pump;

6. The high temperature gas cooled reactor scram post core cooling system as set forth in claim 5, wherein said fourth circulation loop comprises a fourth circulation pipe, a cooling water tower and a cooling water pump;

7. The high temperature gas cooled reactor scram post core cooling system as set forth in claim 6, further comprising a power supply bus, an emergency bus, a battery and a power supply line;