CN115083646B - Method for rapidly cooling steam generator after emergency shutdown of high-temperature gas cooled reactor - Google Patents
Method for rapidly cooling steam generator after emergency shutdown of high-temperature gas cooled reactor Download PDFInfo
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- CN115083646B CN115083646B CN202210717012.0A CN202210717012A CN115083646B CN 115083646 B CN115083646 B CN 115083646B CN 202210717012 A CN202210717012 A CN 202210717012A CN 115083646 B CN115083646 B CN 115083646B
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- 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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Abstract
The invention discloses a method for rapidly cooling a steam generator after emergency shutdown of a high-temperature gas cooled reactor, which comprises the following steps: 1) Discharging the second-circuit water of the steam generator; 2) Naturally cooling the steam generator until the temperature is reduced to 320-360 ℃; 3) The 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 is reduced to 180-193 ℃. According to the method, the superheated steam is introduced into the steam generator, and gradual cooling of the steam generator is realized by controlling gradual cooling of the superheated steam, so that the cooling rate of the steam generator after emergency shutdown of the high-temperature gas cooled reactor is improved, the cooling time is shortened, and the high-temperature gas cooled reactor is facilitated to restart the reactor 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 rapidly cooling a steam generator after emergency shutdown of a high-temperature gas cooled reactor.
Background
Helium is adopted as a coolant in the high-temperature gas cooled reactor, and in normal operation, the helium cooling agent is driven by the main helium fan to flow through the reactor core, so that heat of the reactor core is brought out. The inlet and outlet temperatures of the reactor helium coolant were 250 ℃ and 750 ℃, respectively. After the reactor is in emergency shutdown, the high-temperature gas cooled reactor is designed to be restarted when the temperature of the reactor and the steam generator is reduced to about 200 ℃ in order to ensure safety.
Because the high-temperature gas cooled reactor is assembled into the ceramic reactor inner member by adopting graphite bricks and carbon bricks, the heat capacity of the reactor is large, a special cooling process is not designed in a two-loop, and after the reactor is shut down in an emergency, the reactor and the steam generator are continuously in a high-temperature state before the reactor is shut down. At present, a natural cooling method is mainly adopted, but the cooling rate of a first loop and a second loop of the high-temperature gas cooled reactor is slow by virtue of natural cooling, and the restarting of the reactor takes a long time (about 20 days); or a rapid cooling method is adopted, but the method can cause cold impact to the steam generator due to too rapid temperature drop, and cause certain damage to the steam generator. Therefore, how to increase the cooling speed of the steam generator, avoid damage to the steam generator, and ensure the efficient and orderly cooling of the steam generator is a technical problem to be solved at present.
Disclosure of Invention
The present invention aims to solve at least one of the technical problems in the related art to some extent. Therefore, in one aspect, the embodiment of the invention provides 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 second-circuit water of the steam generator;
2) Naturally cooling the steam generator until the temperature is reduced to 320-360 ℃;
3) The 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 is reduced to 180-193 ℃.
According to the method for rapidly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor, disclosed by the embodiment of the invention, the superheated steam is introduced into the steam generator, and the superheated steam is controlled to be gradually cooled, so that the steam generator is also gradually cooled 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, so that impact damage to the steam generator can be reduced, the steam generator can be safely and quickly cooled after the high-temperature gas cooled reactor is in emergency shutdown, and the safe, stable and reliable operation of equipment is ensured.
In some embodiments, the superheated steam is formed by introducing outlet steam of an auxiliary electric boiler into a steam superheater and heating the steam superheater; the auxiliary electric boiler is sequentially connected with the steam superheater and the steam generator.
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 ℃ at a speed of 4-6 ℃/h. In some embodiments, the flow rate of the superheated steam is controlled to be 2-6t/h, preferably 2t/h.
In some embodiments, the outlet steam of the auxiliary electric boiler has a temperature of 194 ℃ and a pressure of 1.2MPa.
The embodiment of the invention also provides a system for rapidly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor, which comprises a steam generator accident emission tank, an auxiliary electric boiler, a steam superheater, a first drain tank and a condenser;
the steam generator is sequentially connected with the steam superheater and the auxiliary electric boiler;
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 emission tank, the second branch is connected with the first drain tank, and the third branch is connected with the condenser.
The system for quickly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor comprises a steam generator accident discharge tank, an auxiliary electric boiler, a steam superheater, a first drain tank and a condenser, wherein after the emergency shutdown of the high-temperature gas cooled reactor, outlet steam output by the auxiliary electric boiler is filled into the steam superheater, the steam superheater is utilized to heat the outlet steam to form superheated steam, the superheated steam output by the steam superheater enters the steam generator through a pipeline, the temperature of the superheated steam is controlled by the steam superheater, and the temperature of the superheated steam is gradually reduced, so that the temperature in the steam generator is gradually reduced and cooled, the cooling time of the steam generator after the emergency shutdown of the high-temperature gas cooled reactor is greatly shortened, and the high-temperature gas cooled reactor is conveniently restarted as soon as possible; the system for rapidly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor has the advantages of simpler equipment, less equipment quantity, low cost and practical application prospect.
In some embodiments, an electric regulating valve is arranged on a connecting pipeline between the steam generator and the condenser, so as 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 of the steam generator and the first drain tank.
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, the superheated steam is introduced into the steam generator, and the gradual cooling of the superheated steam is controlled by utilizing the steam superheater, 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 rapid restarting of the high-temperature gas cooled reactor is facilitated.
(2) The embodiment of the invention can realize that the temperature of the steam generator can be cooled to meet the re-stacking condition within 5 days by controlling the temperature, the flow rate and the like of the superheated steam, and compared with natural cooling (generally about 20 days), the time is greatly shortened.
(3) Compared with the method for rapidly cooling the steam generator after the emergency shutdown in the related art (the rapid cooling is easy to cause the impact on the steam generator due to the too rapid temperature drop, so that certain equipment damage is caused), the method for rapidly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor in the embodiment of the invention utilizes the superheated steam to gradually cool the steam generator, has small heat capacity, can reduce the impact damage on the steam generator, and ensures the safe, stable and reliable operation of equipment.
(4) According to the system for rapidly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor, disclosed by the embodiment of the invention, the cooling and cooling of the steam generator after the emergency shutdown of the high-temperature gas cooled reactor can be realized by using simple equipment such as the steam generator accident emission tank, the auxiliary electric boiler, the steam superheater, the first drain tank, the condenser, the second drain tank, the auxiliary pipeline, the valve and the like, and the quantity of the equipment is small, the cost is low, and the system has practical application value and obvious economic benefit.
Drawings
FIG. 1 is a schematic 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:
the steam generator is characterized in that the steam generator is 1, the steam generator is 2, the first electric stop valve is 3, the steam generator accident emission tank is 3, the auxiliary electric boiler is 4, the second electric stop valve is 5, the steam superheater is 6, the third electric stop valve is 7, the first drain tank is 8, the electric control valve is 9, the condenser is 10, the fourth electric stop valve is 11, and the second drain tank is 12.
Detailed Description
The following detailed description of embodiments of the invention is exemplary and intended to be illustrative of the invention and not to be construed as limiting the invention.
The following describes a method and a system for quickly cooling a steam generator after emergency shutdown of a high-temperature gas cooled reactor according to an embodiment of the invention with reference to the accompanying drawings.
As shown in fig. 1, in one aspect, the embodiment of the invention provides a method for quickly cooling a steam generator after emergency shutdown of a high-temperature gas cooled reactor, which includes the following steps:
1) Discharging the second-circuit water of the steam generator;
2) Naturally cooling the steam generator until the temperature is reduced to 320-360 ℃;
3) The 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 is reduced to 180-193 ℃.
According to the method for rapidly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor, disclosed by the embodiment of the invention, the superheated steam is introduced into the steam generator, and the superheated steam is controlled to be gradually cooled, so that the steam generator is also gradually cooled 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, so that impact damage to the steam generator can be reduced, the steam generator can be safely and quickly cooled after the high-temperature gas cooled reactor is in emergency shutdown, and the safe, stable and reliable operation of equipment is ensured.
In some embodiments, the superheated steam is formed by introducing outlet steam of the auxiliary electric boiler into a steam superheater and heating the steam superheater; wherein, auxiliary electric boiler connects gradually with steam superheater, steam generator.
In some embodiments, the temperature of the superheated steam is controlled by the steam superheater to gradually decrease from 320-360 ℃ to 180-193 ℃, for example, the temperature of the superheated steam can be controlled by the steam superheater to gradually decrease from 350 ℃ to 180 ℃, or the temperature of the superheated steam can be controlled to gradually decrease from 360 ℃ to 190 ℃, or the temperature of the superheated steam can be controlled to gradually decrease from 350 ℃ to 188 ℃, or the temperature of the superheated steam can be controlled to gradually decrease from 340 ℃ to 182 ℃, etc.; wherein the cooling rate is controlled to be 4-6 ℃/h, such as 4 ℃/h, 5 ℃/h, 6 ℃/h and the like; the temperature of the superheated steam is controlled to gradually decrease, so that the temperature of the steam generator is also gradually decreased and cooled, the heat capacity of the superheated steam is small, the superheated steam can be changed along with the temperature change in the steam generator after being introduced into the steam generator, and the impact damage to the steam generator is reduced.
In some embodiments, the flow rate of superheated steam is controlled to be 2-6t/h, which may be, for example, 2t/h, 2.5t/h, 3t/h, 3.7t/h, 4t/h, 5t/h, 5.5t/h, 6t/h, etc., preferably 2t/h.
In some embodiments, the outlet steam of the auxiliary electric boiler has a temperature of 194 ℃ and a pressure of 1.2MPa.
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 drain tank 8 and a condenser 10;
wherein, steam generator 1 is connected in proper order with steam superheater 6, auxiliary electric boiler 4, specifically: the gas outlet of the auxiliary electric boiler 4 is communicated with the gas inlet of the steam superheater 6, and the auxiliary electric boiler 4 introduces outlet steam into the steam superheater 6 and forms superheated steam after being heated by the steam superheater 6; the gas outlet of the steam superheater 6 is communicated with the gas inlet of the steam generator 1, and superheated steam output by the steam superheater 6 enters the steam generator 1 through a pipeline and slowly cools the steam generator 1 after emergency shutdown so as to achieve good soaking effect;
the bottom outlet of the steam generator 1 is divided into a first branch, a second branch and a third branch, wherein the first branch is connected with the inlet of the steam generator accident discharge tank 3 and is used for discharging secondary water of the steam generator 1; the second branch is connected with the inlet of the first drain tank 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 the inlet of the condenser 10, and the superheated steam cools the steam generator 1 and then is output from the outlet of the steam generator 1, enters the condenser 10 through a pipeline and is condensed.
The system for quickly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor comprises a steam generator accident discharge tank, an auxiliary electric boiler, a steam superheater, a first drain tank and a condenser, wherein after the emergency shutdown of the high-temperature gas cooled reactor, outlet steam output by the auxiliary electric boiler is filled into the steam superheater, the steam superheater is utilized to heat the outlet steam to form superheated steam, the superheated steam output by the steam superheater enters the steam generator through a pipeline, the temperature of the superheated steam is controlled by the steam superheater, and the temperature of the superheated steam is gradually reduced, so that the temperature in the steam generator is gradually reduced and cooled, the cooling time of the steam generator after the emergency shutdown of the high-temperature gas cooled reactor is greatly shortened, and the high-temperature gas cooled reactor is conveniently restarted as soon as possible; the system for rapidly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor has the advantages of simpler equipment, less equipment quantity, low cost and practical application prospect.
In some embodiments, an electric regulating valve 9 is disposed on a connection pipeline between the steam generator 1 and the condenser, so as to regulate the flow of the superheated steam.
In some embodiments, a first electric stop valve 2 is arranged on a connecting pipeline of the steam generator 1 and the steam generator accident discharge tank 3, and when the secondary 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 opening/closing of the second electric stop valve 5 is controlled to control the steam output from the auxiliary electric boiler 4 to be input into the steam superheater 6; a third electric stop valve 7 is provided on the connection line between the steam generator 1 and the first drain tank 8, a small amount of cooling water flows out from the steam generator 1 at the initial stage of cooling the steam generator 1 by superheated steam, at this time, the third electric stop valve 7 is opened to discharge the cooling water in the steam generator 1 into the first drain tank 8, and after the cooling water is discharged, the third electric stop valve 7 is closed.
In some embodiments, the system further comprises a second drain tank 12, the second drain tank 12 is connected with the condenser 10, a fourth electric stop valve 11 is arranged on a connecting pipeline of the second drain tank 12, superheated steam is cooled down the steam generator 1 and then is output from an outlet of the steam generator 1, enters the condenser 10 through a pipeline to be condensed, and condensed water formed in the process is introduced into the second drain tank 12 by controlling the opening/closing of the fourth electric stop valve 11.
The following detailed description of the present embodiment is provided by specific examples:
after the high-temperature gas cooled reactor is in emergency shutdown, the two loops are triggered to be isolated, namely, the inlet valve and the outlet valve of the steam generator 1 are in emergency automatic closing, and the steam generator 1 is in a high-temperature state before the 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 secondary water in the steam generator 1 into 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, starting natural cooling from 571 ℃ at the outlet temperature of the steam generator 1, enabling the initial cooling rate to be high, enabling the cooling rate to be about 6-7 ℃/h, enabling the cooling rate to be slow along with continuous cooling until the cooling rate is reduced to 350 ℃, and ending the natural cooling stage;
3) Superheated steam cooling stage: starting an auxiliary electric boiler 4, and heating steam at the outlet of the auxiliary electric boiler 4 to about 194 ℃ and the pressure of about 1.2MPa; the second electric stop valve 5 is opened, 194 ℃ steam is introduced into the steam superheater 6, the steam superheater 6 is utilized to heat the outlet steam of the auxiliary electric boiler 4 into 350 ℃ superheated steam, the superheated steam is introduced into the steam generator 1 through a pipeline, the electric control valve 9 is utilized to control the flow rate of the superheated steam to be 2t/h, the superheated steam enters the steam generator 1, and the steam generator 1 after emergency shutdown is slowly cooled, so that good soaking effect is achieved.
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, the cooling rate is about 5 ℃/h, and the superheated steam cooling stage is finished until the temperature of the steam generator 1 is reduced to 188 ℃.
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 drain tank 8, and after all the cooling water in the steam generator 1 is discharged, the third electric stop valve 7 is closed; in the subsequent stage of cooling the steam generator 1 by using 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, enters the condenser 10 along with a pipeline to be cooled, and at the moment, the fourth electric stop valve 11 is opened to introduce condensed water formed after cooling 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 is provided and the reactor is provided with a re-start condition, and the whole cooling process takes about 5 days.
In some embodiments of the invention, the natural cooling temperature of the steam generator 1 in step 2) may also be any temperature from 320 to 360 ℃, e.g. the natural cooling temperature of the steam generator 1 may be 360 ℃, 355 ℃, 343 ℃, 340 ℃, 330 ℃, 325 ℃, 320 ℃, etc.
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 gradually cooled down, and in the process, the temperature of the superheated steam is kept close to the temperature of the steam generator 1, so that thermal stress is avoided, and certain damage is caused to the steam generator 1; wherein, when the flow rate of the superheated steam is 3t/h and 4t/h, the superheated steam has better cooling effect on the steam generator 1.
In some embodiments of the present invention, in step 3), the temperature rate of the steam generator 1 when the superheated steam is used for cooling is not too high, otherwise thermal stress is easily caused to cause a certain damage to the steam generator 1 device, so the cooling rate in the embodiments of the present invention is controlled to be 4-6 ℃/h, for example, the cooling rate may be 4 ℃/h, 5 ℃/h, 6 ℃/h, etc.
The method for quickly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor is simpler, and meanwhile, the time for quickly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor can be shortened to about 5 days from about 20 days required by natural cooling; the superheated steam has small heat capacity, so that impact damage to a steam generator can be reduced, the safe, stable and reliable operation of equipment is ensured, and the quick restarting of the high-temperature gas cooled reactor is facilitated; in addition, the method has the advantages of less equipment quantity, low cost and remarkable economic benefit in the system.
In the description of the present invention, it should be understood that the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential", etc. indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings are merely for convenience in describing the present invention and simplifying the description, and do not indicate or imply that the device or element being referred to must have a specific orientation, be configured and operated in a specific orientation, and therefore should not be construed as limiting the present invention.
Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include at least one such feature. In the description of the present invention, the meaning of "plurality" means at least two, for example, two, three, etc., unless specifically defined otherwise.
In the present invention, unless explicitly specified and limited otherwise, the terms "mounted," "connected," "secured," and the like are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally formed; may be mechanically connected, may be electrically connected or may be in communication with each other; either directly or indirectly, through intermediaries, or both, may be in communication with each other or in interaction with each other, unless expressly defined otherwise. The specific meaning of the above terms in the present invention can be understood by those of ordinary skill in the art according to the specific circumstances.
In the present invention, unless expressly stated or limited otherwise, a first feature "up" or "down" a second feature may be the first and second features in direct contact, or the first and second features in indirect contact via an intervening medium. Moreover, a first feature being "above," "over" and "on" a second feature may be a first feature being directly above or obliquely above the second feature, or simply indicating that the first feature is level higher than the second feature. The first feature being "under", "below" and "beneath" the second feature may be the first feature being directly under or obliquely below the second feature, or simply indicating that the first feature is less level than the second feature.
For purposes of this disclosure, the terms "one embodiment," "some embodiments," "example," "a particular example," or "some examples," etc., mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the invention. In this specification, schematic representations of the above terms are not necessarily directed 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, the different embodiments or examples described in this specification and the features of the different embodiments or examples may be combined and combined by those skilled in the art without contradiction.
While embodiments of the present invention have been shown and described above, it will be understood that the above embodiments are illustrative and not to be construed as limiting the invention, and that variations, modifications, alternatives and variations may be made to the above embodiments by one of ordinary skill in the art within the scope of the invention.
Claims (5)
1. The method for rapidly cooling the steam generator after the emergency shutdown of the high-temperature gas cooled reactor is characterized by comprising the following steps of:
1) Discharging the second-circuit water of the steam generator;
2) Naturally cooling the steam generator until the temperature is reduced to 320-360 ℃;
3) Introducing the superheated steam into a steam generator, and gradually reducing the temperature of the superheated steam until the temperature of the steam generator is reduced to 180-193 ℃;
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 sequentially connected with the steam superheater and the steam generator;
the temperature of the superheated steam is controlled to be gradually reduced from 320-360 ℃ to 180-193 ℃ through the steam superheater, and the temperature reduction rate is 4-6 ℃/h; the flow rate of the superheated steam is controlled to be 2-6t/h;
the temperature of the outlet steam of the auxiliary electric boiler is 194 ℃, and the pressure is 1.2MPa.
2. The method for quickly cooling a steam generator after emergency shutdown of a high temperature gas cooled reactor according to claim 1, wherein the flow rate of the superheated steam is controlled to be 2t/h.
3. A system for rapid cooling of a steam generator after emergency shutdown of a high temperature gas cooled reactor, characterized by being used for implementing the method as claimed in claim 1 or 2, comprising a steam generator, a steam generator accident discharge tank, an auxiliary electric boiler, a steam superheater, a first drain tank and a condenser;
the steam generator is sequentially connected with the steam superheater and the auxiliary electric boiler;
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;
an electric regulating valve is arranged on a connecting pipeline of the steam generator and the condenser and used for regulating the flow of superheated steam.
4. The system for quickly cooling a steam generator after emergency shutdown of a high temperature gas cooled reactor according to claim 3, wherein 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 of the steam generator and the first drain tank.
5. The system for rapidly cooling a steam generator after emergency shutdown of a high temperature gas cooled reactor according to claim 3, further comprising a second drain tank, wherein 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.
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