CN115083646A - Method for quickly cooling steam generator after emergency shutdown of high-temperature gas cooled reactor - Google Patents
Method for quickly cooling steam generator after emergency shutdown of high-temperature gas cooled reactor Download PDFInfo
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- 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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Abstract
The invention discloses a method for quickly cooling a steam generator after emergency shutdown of a high-temperature gas cooled reactor, which comprises the following steps: 1) discharging the two-loop water of the steam generator; 2) naturally cooling the steam generator until the temperature is reduced to 320-360 ℃; 3) superheated steam is introduced into the steam generator and the temperature of the superheated steam is gradually reduced until the temperature of the steam generator drops to 180-. According to the method, the superheated steam is introduced into the steam generator, and the steam generator is gradually cooled by controlling the superheated steam, so that the gradual cooling of the steam generator is realized, the cooling rate of the steam generator after the high-temperature gas-cooled reactor is emergently stopped is increased, the cooling time is shortened, and the high-temperature gas-cooled reactor is favorable for restarting as soon as possible; and at the same time impact damage to the steam generator can be reduced.
Description
Technical Field
The invention belongs to the technical field of nuclear power, and particularly relates to a method for quickly cooling a steam generator after emergency shutdown of a high-temperature gas cooled reactor.
Background
The high-temperature gas cooled reactor adopts helium as a coolant, and when the high-temperature gas cooled reactor is in normal operation, the main helium fan drives the helium to flow through the reactor core and take out heat of the reactor core. The reactor helium coolant inlet and outlet temperatures were 250 ℃ and 750 ℃ respectively. After the emergency shutdown of the reactor, in order to ensure safety, the high-temperature gas cooled reactor is designed to be restarted when the temperature of the reactor and a steam generator is reduced to about 200 ℃.
Because the high-temperature gas cooled reactor is assembled into a ceramic reactor internal component by adopting graphite bricks and carbon bricks, the thermal capacity of the reactor is large, and a special cooling process is not designed in the first loop and the second loop, after emergency shutdown, the reactor and the steam generator are continuously in a high-temperature state before shutdown. At present, a natural cooling method is mainly adopted, but natural cooling is relied on, the cooling rate of a first loop and a second loop of a high-temperature gas-cooled reactor is slow, and the reactor needs to spend a long time (about 20 days) for restarting; or a rapid cooling method is adopted, but the method can cause certain damage to the steam generator due to cold impact on the steam generator caused by too rapid temperature drop. Therefore, how to improve the cooling rate of the steam generator and avoid damaging the steam generator, and ensure the efficient and orderly cooling of the steam generator is a technical problem which needs to be solved urgently at present.
Disclosure of Invention
The present invention is directed to solving, at least to some extent, one of the technical problems in the related art. Therefore, in one aspect, an embodiment of the present invention provides a method for rapidly cooling a steam generator after an emergency shutdown of a high temperature gas cooled reactor, including the following steps:
1) discharging the two-loop water of the steam generator;
2) naturally cooling the steam generator until the temperature is reduced to 320-360 ℃;
3) superheated steam is introduced into the steam generator and the temperature of the superheated steam is gradually reduced until the temperature of the steam generator drops to 180-.
According to the method for rapidly cooling the steam generator after the emergency shutdown of the high-temperature gas-cooled reactor, superheated steam is introduced into the steam generator and is controlled to be gradually cooled down, so that the steam generator is gradually cooled down to the target temperature, the cooling time of the steam generator after the emergency shutdown of the high-temperature gas-cooled reactor can be greatly shortened, and the high-temperature gas-cooled reactor can be conveniently restarted as soon as possible; the superheated steam adopted in the embodiment of the invention has small heat capacity and can change along with the temperature change in the steam generator after being introduced into the steam generator, thereby reducing the impact damage to the steam generator, ensuring that the steam generator can be safely and quickly cooled after the high-temperature gas cooled reactor is in emergency shutdown, and ensuring the safe, stable and reliable operation of equipment.
In some embodiments, the superheated steam is formed by introducing outlet steam of an auxiliary electric boiler into a steam superheater and heating the outlet steam by the steam superheater; the auxiliary electric boiler is connected with the steam superheater and the steam generator in sequence.
In some embodiments, the temperature of the superheated steam is controlled by the steam superheater to be gradually reduced from 320-360 ℃ to 180-193 ℃, and the temperature reduction rate is 4-6 ℃/h. In some embodiments, the flow rate of the superheated steam is controlled to be 2-6t/h, preferably 2 t/h.
In some embodiments, the outlet steam of the auxiliary electric boiler has a temperature of 194 ℃ and a pressure of 1.2 MPa.
The embodiment of the invention also provides a system for quickly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor, which comprises a steam generator accident discharge tank, an auxiliary electric boiler, a steam superheater, a first steam trap and a condenser, wherein the steam generator accident discharge tank is connected with the auxiliary electric boiler;
the steam generator is connected with the steam superheater and the auxiliary electric boiler in sequence;
the bottom outlet of the steam generator is divided into a first branch, a second branch and a third branch, the first branch is connected with the steam generator accident discharge tank, the second branch is connected with the first drain tank, and the third branch is connected with the condenser.
The system for rapidly cooling the steam generator after the high-temperature gas cooled reactor is emergently stopped comprises a steam generator accident discharge tank, an auxiliary electric boiler, a steam superheater, a first steam trap and a steam condenser, wherein after the high-temperature gas cooled reactor is emergently stopped, outlet steam output by the auxiliary electric boiler is filled into the steam superheater and is heated by the steam superheater to form superheated steam, the superheated steam output by the steam superheater enters the steam generator through a pipeline, and the temperature of the superheated steam is controlled by the steam superheater so that the temperature of the superheated steam is gradually reduced, the temperature in the steam generator is gradually reduced and cooled, the cooling time of the steam generator after the high-temperature gas cooled reactor is emergently stopped is greatly shortened, and the high-temperature gas cooled reactor is convenient to restart the reactor as soon as possible; and the equipment used in the system for quickly cooling the steam generator after the high-temperature gas cooled reactor is in emergency shutdown is simple, the quantity of the equipment is small, the cost is low, and the system has practical application prospect.
In some embodiments, an electric control valve is arranged on a connection pipeline between the steam generator and the condenser to regulate the flow of the superheated steam.
In some embodiments, a first electric stop valve is arranged on a connecting pipeline of the steam generator and the steam generator accident discharge tank; a second electric stop valve is arranged on a connecting pipeline of the steam superheater and the auxiliary electric boiler; and a third electric stop valve is arranged on a connecting pipeline between the steam generator and the first steam trap.
In some embodiments, the system further comprises a second drain tank, the second drain tank is connected with the condenser, and a fourth electric stop valve is arranged on a connecting pipeline of the second drain tank.
The invention has the advantages and beneficial effects that:
(1) according to the method for rapidly cooling the steam generator after the emergency shutdown of the high-temperature gas-cooled reactor, superheated steam is introduced into the steam generator, and the steam superheater is used for controlling the gradual cooling of the superheated steam, so that the gradual cooling of the steam generator is realized, the cooling time of the steam generator after the emergency shutdown of the high-temperature gas-cooled reactor is shortened, and the high-temperature gas-cooled reactor is favorable for restarting as soon as possible.
(2) According to the embodiment of the invention, the temperature, the flow and the like of the superheated steam are controlled, so that the temperature of the steam generator can be cooled to meet the condition of restarting the reactor within 5 days, and compared with natural cooling (generally, the time is shortened by about 20 days).
(3) Compared with the method for quickly cooling the steam generator after the emergency shutdown in the related art (the quick cooling is easy to cause that the steam generator is impacted due to too quick temperature reduction to cause certain equipment damage), the method for quickly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor disclosed by the embodiment of the invention gradually cools the steam generator by using the superheated steam, has small heat capacity of the superheated steam, can reduce the impact damage to the steam generator, and ensures the safe, stable and reliable operation of the equipment.
(4) According to the system for quickly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor, the steam generator accident discharge tank, the auxiliary electric boiler, the steam superheater, the first steam trap, the condenser, the second steam trap, the auxiliary pipeline, the valve and other simple equipment are only utilized to cool the steam generator after the emergency shutdown of the high-temperature gas cooled reactor, and the system is small in equipment quantity, low in cost and has practical application value and remarkable economic benefit.
Drawings
Fig. 1 is a schematic structural diagram of a system for rapidly cooling a steam generator after an emergency shutdown of a high temperature gas cooled reactor according to an embodiment of the present invention.
Reference numerals:
1 is steam generator, 2 is first electric stop valve, 3 is steam generator accident discharge jar, 4 is supplementary electric boiler, 5 is second electric stop valve, 6 is steam superheater, 7 is third electric stop valve, 8 is first drain tank, 9 is electric control valve, 10 is the condenser, 11 is fourth electric stop valve, 12 is the second drain tank.
Detailed Description
The following detailed description of embodiments of the invention is intended to be illustrative, and not to be construed as limiting the invention.
The following describes a method and a system for fast cooling a steam generator after an emergency shutdown of a high temperature gas cooled reactor according to an embodiment of the present invention with reference to the accompanying drawings.
As shown in fig. 1, in one aspect, the embodiment of the present invention provides a method for rapidly cooling a steam generator after an emergency shutdown of a high temperature gas cooled reactor, including the following steps:
1) discharging the two-loop water of the steam generator;
2) naturally cooling the steam generator until the temperature is reduced to 320-360 ℃;
3) superheated steam is introduced into the steam generator and the temperature of the superheated steam is gradually reduced until the temperature of the steam generator drops to 180-.
According to the method for rapidly cooling the steam generator after the emergency shutdown of the high-temperature gas-cooled reactor, superheated steam is introduced into the steam generator and is controlled to be gradually cooled down, so that the steam generator is gradually cooled down to the target temperature, the cooling time of the steam generator after the emergency shutdown of the high-temperature gas-cooled reactor can be greatly shortened, and the high-temperature gas-cooled reactor can be conveniently restarted as soon as possible; the superheated steam adopted in the embodiment of the invention has small heat capacity and can change along with the temperature change in the steam generator after being introduced into the steam generator, thereby reducing the impact damage to the steam generator, ensuring that the steam generator can be safely and quickly cooled after the high-temperature gas cooled reactor is in emergency shutdown, and ensuring the safe, stable and reliable operation of equipment.
In some embodiments, the superheated steam is formed by introducing outlet steam of the auxiliary electric boiler into a steam superheater and heating the outlet steam by the steam superheater; wherein, the auxiliary electric boiler is connected with the steam superheater and the steam generator in sequence.
In some embodiments, the temperature of the superheated steam is controlled by the steam superheater to be gradually reduced from 320-360 ℃ to 180-193 ℃, for example, the temperature of the superheated steam can be controlled by the steam superheater to be gradually reduced from 350 ℃ to 180 ℃, or the temperature of the superheated steam is controlled to be gradually reduced from 360 ℃ to 190 ℃, or the temperature of the superheated steam is controlled to be gradually reduced from 350 ℃ to 188 ℃, or the temperature of the superheated steam is controlled to be gradually reduced from 340 ℃ to 182 ℃, and the like; wherein the cooling rate is controlled to be 4-6 ℃/h, for example, 4 ℃/h, 5 ℃/h, 6 ℃/h and the like; the temperature of the superheated steam is controlled to gradually fall, so that the temperature of the steam generator is gradually lowered and cooled, the heat capacity of the superheated steam is small, the superheated steam is led into the steam generator and then changes along with the temperature change in the steam generator, and impact damage to the steam generator is reduced.
In some embodiments, the flow rate of the superheated steam is controlled to be 2-6t/h, for example, 2t/h, 2.5t/h, 3t/h, 3.7t/h, 4t/h, 5t/h, 5.5t/h, 6t/h, etc., preferably 2 t/h.
In some embodiments, the outlet steam of the auxiliary electric boiler has a temperature of 194 ℃ and a pressure of 1.2 MPa.
The embodiment of the invention also provides a system for quickly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor, which comprises a steam generator accident discharge tank 3, an auxiliary electric boiler 4, a steam superheater 6, a first steam trap tank 8 and a condenser 10;
wherein, steam generator 1 connects gradually with steam superheater 6, supplementary electric boiler 4, specifically is: a gas outlet of the auxiliary electric boiler 4 is communicated with a gas inlet of the steam superheater 6, outlet steam is introduced into the steam superheater 6 by the auxiliary electric boiler 4 and is heated by the steam superheater 6 to form superheated steam; the gas outlet of the steam superheater 6 is communicated with the gas inlet of the steam generator 1, superheated steam output by the steam superheater 6 enters the steam generator 1 through a pipeline, and the steam generator 1 after scram is slowly cooled so as to achieve a good soaking effect;
the bottom outlet of the steam generator 1 is divided into a first branch, a second branch and a third branch, the first branch is connected with the inlet of the steam generator accident discharge tank 3 and used for discharging the two-loop water of the steam generator 1; the second branch is connected with the inlet of the first steam trap 8 and is used for collecting cooling water generated in the initial cooling process of the steam generator 1; the third branch is connected with an inlet of the condenser 10, superheated steam is output from an outlet of the steam generator 1 after cooling the steam generator 1, and the superheated steam enters the condenser 10 through a pipeline for condensation.
The system for rapidly cooling the steam generator after the high-temperature gas cooled reactor is emergently stopped comprises a steam generator accident discharge tank, an auxiliary electric boiler, a steam superheater, a first steam trap and a steam condenser, wherein after the high-temperature gas cooled reactor is emergently stopped, outlet steam output by the auxiliary electric boiler is filled into the steam superheater and is heated by the steam superheater to form superheated steam, the superheated steam output by the steam superheater enters the steam generator through a pipeline, and the temperature of the superheated steam is controlled by the steam superheater so that the temperature of the superheated steam is gradually reduced, the temperature in the steam generator is gradually reduced and cooled, the cooling time of the steam generator after the high-temperature gas cooled reactor is emergently stopped is greatly shortened, and the high-temperature gas cooled reactor is convenient to restart the reactor as soon as possible; in addition, the equipment used in the system for quickly cooling the steam generator after the high-temperature gas cooled reactor is in emergency shutdown is simple, the number of the equipment is small, the cost is low, and the system has practical application prospect.
In some embodiments, an electric control valve 9 is disposed on a connection pipeline between the steam generator 1 and the condenser to regulate the flow of the superheated steam.
In some embodiments, a first electric stop valve 2 is arranged on a connecting pipeline between the steam generator 1 and the steam generator emergency discharge tank 3, and when the two-loop water of the steam generator 1 is discharged, the first electric stop valve 2 is closed; a second electric stop valve 5 is arranged on a connecting pipeline of the steam superheater 6 and the auxiliary electric boiler 4, and the outlet steam of the auxiliary electric boiler 4 is controlled to be input into the steam superheater 6 by controlling the opening/closing of the second electric stop valve 5; the third electric stop valve 7 is arranged on the connecting pipeline between the steam generator 1 and the first steam trap 8, a small amount of cooling water flows out of the steam generator 1 at the initial stage of cooling the steam generator 1 by superheated steam, the third electric stop valve 7 is opened at the moment, the cooling water in the steam generator 1 is discharged into the first steam trap 8, and the third electric valve 7 is closed after the cooling water is discharged.
In some embodiments, the system further includes a second steam trap 12, the second steam trap 12 is connected to the condenser 10, a fourth electric stop valve 11 is disposed on a connection pipeline of the second steam trap 12, the superheated steam cools the steam generator 1 and then is output from an outlet of the steam generator 1, and enters the condenser 10 through a pipeline for condensation, and the condensed water formed in the process is introduced into the second steam trap 12 by controlling the opening/closing of the fourth electric stop valve 11.
The present solution is described in detail below by means of specific examples:
after the high-temperature gas cooled reactor is in emergency shutdown, two loops are triggered to be isolated, namely the inlet valve and the outlet valve of the steam generator 1 are automatically closed in emergency, and the steam generator 1 is continuously in a high-temperature state before shutdown. At the moment, the high-temperature gas cooled reactor enters an emergency shutdown cooling state, and the specific scheme is as follows:
1) the steam generator 1 discharges water: opening the first electric stop valve 2, discharging the two-loop water in the steam generator 1 to the steam generator accident discharge tank 3, and ending the water discharge stage;
2) the steam generator 1 is naturally cooled: opening a cabin door of the steam generator 1, enabling the steam generator 1 to enter a natural cooling stage, naturally cooling the outlet temperature of the steam generator 1 from 571 ℃, wherein the initial cooling rate is high, the cooling rate is about 6-7 ℃/h, and the cooling rate is slowed down along with continuous cooling until the temperature is reduced to 350 ℃, and the natural cooling stage is ended;
3) a superheated steam cooling stage: starting the auxiliary electric boiler 4, and heating the steam at the outlet of the auxiliary electric boiler 4 to about 194 ℃ and the pressure of about 1.2 MPa; the second electric stop valve 5 is opened, 194 ℃ steam is introduced into the steam superheater 6, outlet steam of the auxiliary electric boiler 4 is heated into 350 ℃ superheated steam by the steam superheater 6, the superheated steam is introduced into the steam generator 1 through a pipeline, the flow of the superheated steam is controlled to be 2t/h by the electric control valve 9, the superheated steam enters the steam generator 1, and the steam generator 1 after emergency shutdown is slowly cooled to achieve a good heat soaking effect.
In the process of cooling the steam generator 1 by using the superheated steam, the temperature of the superheated steam is controlled to gradually decrease from 350 ℃ through the steam superheater 6, so that the temperature of the steam generator 1 is also gradually decreased and cooled, wherein the temperature decrease rate is about 5 ℃/h until the temperature of the steam generator 1 decreases to 188 ℃, and the superheated steam cooling stage is finished.
In the initial stage of cooling the steam generator 1 by using superheated steam, a small amount of cooling water is generated in the steam generator 1, at this time, the third electric stop valve 7 is kept in an open state, the cooling water in the steam generator 1 is discharged into the first steam trap 8, and after all the cooling water in the steam generator 1 is discharged, the third electric valve 7 is closed; at the subsequent stage of cooling the steam generator 1 by using the superheated steam, no cooling water is generated in the steam generator 1, the superheated steam is still in a gas state after cooling the steam generator 1, is discharged through an outlet of the steam generator 1 and enters the condenser 10 along with a pipeline for cooling, at the moment, the fourth electric stop valve 11 is opened, and condensed water formed after cooling is introduced into the second drain tank 12.
When the temperature of the steam generator 1 is reduced to 188 ℃, the water injection of the steam generator 1 and the reactor restart conditions are met, and the whole cooling process takes about 5 days.
In some embodiments of the present invention, the natural cooling temperature of the steam generator 1 in the step 2) may be any temperature of 320 ℃ and 360 ℃, for example, the natural cooling temperature of the steam generator 1 may be 360 ℃, 355 ℃, 343 ℃, 340 ℃, 330 ℃, 325 ℃, 320 ℃ or the like.
In some embodiments of the present invention, in step 3), the steam superheater 6 is used to heat the outlet steam of the auxiliary electric boiler 4 to form superheated steam, and the superheated steam is introduced into the steam generator 1 through a pipeline, and the temperature of the superheated steam is controlled to gradually decrease, so that the temperature of the steam generator 1 is also gradually decreased and cooled, in this process, the temperature of the superheated steam is kept close to the temperature of the steam generator 1, so as to prevent thermal stress from causing a certain damage to the steam generator 1; wherein, when the flow rate of the superheated steam is 3t/h and 4t/h, the superheated steam also has better cooling effect on the steam generator 1.
In some embodiments of the present invention, in step 3), the temperature rate of cooling the steam generator 1 by using superheated steam is not too high, otherwise, thermal stress is easily caused to cause certain damage to the steam generator 1, so the temperature rate in the embodiment of the present invention is controlled to be 4-6 ℃/h, for example, the temperature rate may be 4 ℃/h, 5 ℃/h, 6 ℃/h, and the like.
The method for rapidly cooling the steam generator after the high-temperature gas-cooled reactor is emergently stopped is simple, and meanwhile, the time for rapidly cooling the steam generator after the high-temperature gas-cooled reactor is emergently stopped can be shortened to about 5 days from about 20 days required by natural cooling; the heat capacity of the superheated steam is small, so that impact damage to a steam generator can be reduced, the safe, stable and reliable operation of equipment is ensured, and the high-temperature gas cooled reactor is favorable for quickly restarting; in addition, the method has the advantages of small equipment quantity in the used system, low cost and remarkable economic benefit.
In the description of the present invention, 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 invention 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 invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present invention, "a plurality" means at least two, e.g., two, three, etc., unless explicitly specified otherwise.
In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," "secured," and the like are to be construed broadly and can, for example, be fixedly connected, detachably connected, or integrally formed; may be mechanically coupled, may be electrically coupled or may be in communication with each other; they may be directly connected or indirectly connected through intervening media, or they may be connected internally or in any other suitable relationship, unless expressly stated otherwise. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
In the present invention, unless otherwise expressly stated or limited, the first feature "on" or "under" the second feature may be directly contacting the first and second features or indirectly contacting the first and second features through an intermediate. Also, a first feature "on," "over," and "above" a second feature may be directly or diagonally above the second feature, or may simply indicate that the first feature is at a higher level than the second feature. A first feature being "under," "below," and "beneath" a second feature may be directly under or obliquely under the first feature, or may simply mean that the first feature is at a lesser elevation than the second feature.
In the present disclosure, the terms "one embodiment," "some embodiments," "an example," "a specific example," or "some examples" and the like mean that a specific feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present disclosure. In this specification, the schematic representations of the terms used above are not necessarily intended to refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, various embodiments or examples and features of different embodiments or examples described in this specification can be combined and combined by one skilled in the art without contradiction.
Although embodiments of the present invention have been shown and described above, it will be understood that the above embodiments are exemplary and not to be construed as limiting the present invention, and that changes, modifications, substitutions and alterations can be made to the above embodiments by those of ordinary skill in the art within the scope of the present invention.
Claims (10)
1. A method for quickly cooling a steam generator after emergency shutdown of a high-temperature gas cooled reactor is characterized by comprising the following steps:
1) discharging the two-loop water of the steam generator;
2) naturally cooling the steam generator until the temperature is reduced to 320-360 ℃;
3) superheated steam is introduced into the steam generator and the temperature of the superheated steam is gradually reduced until the temperature of the steam generator drops to 180-.
2. The method for rapidly cooling the steam generator after the emergency shutdown of the high temperature gas cooled reactor according to claim 1, wherein the superheated steam is formed by introducing outlet steam of an auxiliary electric boiler into a steam superheater and heating the outlet steam by the steam superheater; the auxiliary electric boiler is connected with the steam superheater and the steam generator in sequence.
3. The method for rapidly cooling the steam generator after the scram of the high temperature gas cooled reactor as claimed in claim 1 or 2, wherein the temperature of the superheated steam is controlled by the steam superheater to be gradually cooled from 320-360 ℃ to 180-193 ℃, and the cooling rate is 4-6 ℃/h.
4. The method for rapid cooling of the steam generator after scram of the high temperature gas cooled reactor according to claim 1, wherein the flow rate of the superheated steam is controlled to be 2-6 t/h.
5. The method for rapid cooling of the steam generator after scram of the high temperature gas cooled reactor according to claim 4, wherein the flow rate of the superheated steam is controlled to be 2 t/h.
6. The method for rapidly cooling the steam generator after the scram of the high temperature gas cooled reactor according to claim 2, wherein the temperature of the outlet steam of the auxiliary electric boiler is 194 ℃, and the pressure is 1.2 MPa.
7. A system for rapidly cooling a steam generator after emergency shutdown of a high-temperature gas-cooled reactor is characterized by comprising a steam generator accident discharge tank, an auxiliary electric boiler, a steam superheater, a first drain tank and a condenser;
the steam generator is connected with the steam superheater and the auxiliary electric boiler in sequence;
the bottom outlet of the steam generator is divided into a first branch, a second branch and a third branch, the first branch is connected with the steam generator accident discharge tank, the second branch is connected with the first drain tank, and the third branch is connected with the condenser.
8. The system for rapidly cooling the steam generator after the scram of the high temperature gas cooled reactor as claimed in claim 7, wherein an electric control valve is disposed on a connection pipeline between the steam generator and the condenser for adjusting the flow of the superheated steam.
9. The system for rapidly cooling the steam generator after the scram of the high temperature gas cooled reactor according to claim 7, wherein a first electric stop valve is arranged on a connecting pipeline between the steam generator and the steam generator emergency discharge tank; a second electric stop valve is arranged on a connecting pipeline of the steam superheater and the auxiliary electric boiler; and a third electric stop valve is arranged on a connecting pipeline between the steam generator and the first steam trap.
10. The system for rapidly cooling the steam generator after the emergency shutdown of the high temperature gas cooled reactor according to claim 7, further comprising a second steam trap, wherein the second steam trap is connected to the condenser, and a fourth electric stop valve is arranged on a connecting pipeline of the second steam trap and the condenser.
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