CN215927489U

CN215927489U - Non-nuclear steam flushing system of high-temperature gas cooled reactor

Info

Publication number: CN215927489U
Application number: CN202122481614.4U
Authority: CN
Inventors: 徐伟强; 马喜强; 叶林; 赵峰; 彭帅; 刘汝卫; 徐校飞; 李源; 赵敬锴; 李振宇; 王磊; 崔鹏; 黄鹏
Original assignee: Huaneng Shandong Shidaobay Nuclear Power Co Ltd
Current assignee: Huaneng Shandong Shidaobay Nuclear Power Co Ltd
Priority date: 2021-10-14
Filing date: 2021-10-14
Publication date: 2022-03-01
Anticipated expiration: 2031-10-14

Abstract

The utility model relates to the technical field of nuclear power, in particular to a non-nuclear steam rush-transfer system of a high-temperature gas cooled reactor, which comprises: the steam generator, the superheater, the steam-water separator and the main steam pipeline are sequentially communicated along the steam conveying direction, and the main steam pipeline is connected with the mechanism to be flushed. The utility model provides a high-temperature gas cooled reactor non-nuclear steam rush system which can continuously supply steam meeting parameter requirements to carry out turbine rush.

Description

Non-nuclear steam flushing system of high-temperature gas cooled reactor

Technical Field

The utility model relates to the technical field of nuclear power, in particular to a non-nuclear steam rush-transfer system of a high-temperature gas cooled reactor.

Background

The non-nuclear steam scouring is a main test project of a nuclear power plant during construction and debugging, and the non-nuclear steam is used for pushing a steam turbine to scour before the reactor is charged, so that the production and installation quality of the steam turbine is checked, and related defects of the steam turbine are discovered and treated in advance, so that the nuclear steam can be used for scouring and grid-connected power generation after the reactor is charged.

At present, a pressurized water reactor nuclear power plant mainly uses the main pump of a loop to continuously operate, the coolant of the loop is driven to circulate, the coolant of the loop is heated through long-term circulation, the heated coolant is used for heating the feed water of two loops through a steam generator to generate steam, and therefore the steam turbine is flushed.

In the high-temperature gas cooled reactor, because the coolant of the primary loop is helium and the primary loop is driven by the fan to circulate, the heat generated by the rotation of the primary helium fan cannot heat the feed water of the secondary loop to meet the parameters of the turbine running, and the steam parameters generated by the auxiliary electric boiler of the high-temperature gas cooled reactor are too low to meet the running conditions of the turbine.

SUMMERY OF THE UTILITY MODEL

Therefore, the technical problem to be solved by the utility model is that steam meeting parameter requirements cannot be continuously supplied due to the heating hysteresis of the main pump, and the turbine cannot be rushed in a conventional non-nuclear steam rushing mode of a pressurized water reactor, so that a high-temperature gas-cooled reactor non-nuclear steam rushing system capable of continuously supplying steam meeting parameter requirements to rush the turbine is provided.

In order to solve the above technical problem, the present invention provides a high temperature gas cooled reactor non-nuclear steam flushing system, comprising:

the steam generator, the superheater, the steam-water separator and the main steam pipeline are sequentially communicated along the steam conveying direction, and the main steam pipeline is connected with the mechanism to be flushed.

Optionally, the steam generator further comprises at least one first branch steam pipeline arranged between the main steam pipeline and the mechanism to be flushed.

Optionally, the first branch steam pipeline is provided with a first valve and at least two second valves, and the at least two second valves are connected in parallel.

Optionally, the steam generator further comprises a second branch steam pipeline arranged between the main steam pipeline and the mechanism to be flushed, and the second branch steam pipeline is connected with the first branch steam pipeline in parallel.

Optionally, a third valve is arranged on the second branch steam pipeline.

Optionally, a condenser is arranged between the third valve and the mechanism to be flushed.

Optionally, a third steam pipeline is further arranged between the steam-water separator and the condenser.

Optionally, the steam generator is an auxiliary electric boiler.

The technical scheme of the utility model has the following advantages:

1. the utility model provides a high-temperature gas cooled reactor non-nuclear steam transfer system, which is provided with a steam generator and a superheater along the steam conveying direction, saturated steam generated by the steam generator is heated by the superheater into superheated steam with a certain superheat degree, and the operating parameters of the steam generator and the superheater can be adjusted according to requirements to meet the transfer requirements under different working conditions; the steam generator and the superheater can continuously and stably operate, so that continuous steam meeting the requirement can be provided to flush and rotate the mechanism to be flushed, and the constant-speed operation of the mechanism to be flushed is realized.

2. The utility model provides a high-temperature gas cooled reactor non-nuclear steam flushing system, wherein a first valve and at least two second valves are arranged on a first steam pipeline, the at least two second valves are connected in parallel, and the rotating speed of a mechanism to be flushed can be controlled through the first valve and the second valve, so that the mechanism to be flushed can be flushed according to the required speed.

3. According to the non-nuclear steam flushing system for the high-temperature gas cooled reactor, a second branch steam pipeline is arranged between the main steam pipeline and the mechanism to be flushed, a third valve is arranged on the second branch steam pipeline, the third valve can be used for pressure control, the pressure of the main steam pipeline is controlled to be stabilized within a certain limit value, and the flushing parameters are guaranteed to be stable.

4. According to the high-temperature gas cooled reactor non-nuclear steam flushing system provided by the utility model, a third steam pipeline is also arranged between the steam-water separator and the condenser, partial steam from the steam-water separator can be directly discharged to the condenser through a bypass, and the rotating speed of a mechanism to be flushed can be controlled by matching with the first valve by adjusting the steam discharge amount of the bypass, so that the stable operation of the mechanism to be flushed at the set rotating speed is realized.

Drawings

In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, and it is obvious that the drawings in the following description are some embodiments of the present invention, and other drawings can be obtained by those skilled in the art without creative efforts.

FIG. 1 is a schematic diagram of a non-nuclear steam flushing system of a high temperature gas cooled reactor;

FIG. 2 is a schematic diagram of an alternate embodiment of a high temperature gas cooled reactor non-nuclear steam flushing system;

description of reference numerals:

1-a steam generator; 2-a superheater; 3-a steam-water separator; 4-main steam line;

5-a first valve; 6-a second valve; 7-high pressure cylinder; 8-low pressure cylinder; 9-a condenser;

10-a third valve; 11-a steam turbine; 12-a shaft seal arrangement;

Detailed Description

The technical solutions of the present invention will be described clearly and completely with reference to the accompanying drawings, and it should be understood that the described embodiments are some, but not all embodiments of the present invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.

In the description of the present invention, it should be noted that the terms "center", "upper", "lower", "left", "right", "vertical", "horizontal", "inner", "outer", etc., indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, and are only for convenience of description and simplicity of description, but do not indicate or imply that the device or element being referred to must have a particular orientation, be constructed and operated in a particular orientation, and thus, should not be construed as limiting the present invention. Furthermore, the terms "first," "second," and "third" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.

In the description of the present invention, it should be noted that, unless otherwise explicitly specified or limited, the terms "mounted," "connected," and "connected" are to be construed broadly, e.g., as meaning either a fixed connection, a removable connection, or an integral connection; can be mechanically or electrically connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. The specific meanings of the above terms in the present invention can be understood in specific cases to those skilled in the art.

In addition, the technical features involved in the different embodiments of the present invention described below may be combined with each other as long as they do not conflict with each other.

Fig. 1 shows a schematic diagram of a high temperature gas cooled reactor non-nuclear steam flushing system, which is used for flushing a steam turbine, and includes a steam generator 1, a superheater 2, a steam-water separator 3 and a main steam pipeline 4, which are sequentially communicated with each other along a steam conveying direction, and the main steam pipeline 4 is connected with a mechanism to be flushed. The mechanism to be flushed is a steam turbine 11 which comprises a high-pressure cylinder 7 and a low-pressure cylinder 8 which are communicated with each other.

The steam generator 1 is an auxiliary electric boiler for generating saturated steam.

Two first steam pipelines are arranged between the main steam pipeline 4 and the mechanism to be flushed in parallel, each first steam pipeline is provided with a first valve 5 and two second valves 6, and at least two second valves 6 are connected in parallel. The outlet of the first steam pipeline is communicated with a high-pressure cylinder 7.

And a second steam pipeline is arranged between the main steam pipeline 4 and the mechanism to be flushed and rotated, the second steam pipeline is connected with the first steam pipeline in parallel, a third valve 10 is arranged on the second steam pipeline, and the third valve 10 is connected with a low-pressure cylinder 8 through a condenser 9.

When the high-temperature gas cooled reactor non-nuclear steam flushing system works, the steam generator 1 is started to generate steam, the steam enters the condenser 9 through the heater 2, the steam-water separator 3, the main steam pipeline 4 and the third valve 10 to perform primary heating of the secondary loop flushing loop, and at the moment, the first valve 5 and the second valve 6 are kept closed. After the primary heating pipe is finished, the superheater 2 is started to heat the steam generated by the steam generator 1, the superheat degree of the impulse steam is gradually increased so that the superheat degree meets the air inlet requirement of a steam turbine, the impulse circuit is further heated, and the steam generator 1 and the superheater 2 are adjusted in an automatic power control mode at the moment. After the warm pipe is finished, the second valve 6 is opened, the first valve 5 is slowly opened to control the rotating speed of the steam turbine to perform steam turbine running, the steam enters the high-pressure cylinder 7 to do work and then enters the low-pressure cylinder 8 to do work, the steam is discharged into the condenser 9 to be condensed into water after the work is finished, and finally the water is discharged out of the system. In addition, partial steam after passing through the steam-water separator 3 can be directly discharged to the condenser 9 through the bypass, and the steam discharge amount of the bypass is adjusted to be matched with the first valve 5 to control the rotating speed of the steam turbine, so that the steam turbine can stably operate at the set rotating speed.

The Na content of the steam generated by the auxiliary electric boiler is 2.1 mu g/L and is less than the impulse steam quality (less than or equal to 20 mu g/L), and the Fe content is 10.4 mu g/L and is less than the impulse steam quality (less than or equal to 30 mu g/L). The steam parameters at the outlet of the auxiliary electric boiler are 1MPa and 193 ℃, the flow rate is about 32-34t/h, the impulse rotation of a steam turbine cannot be realized, the steam turbine is heated by the heat device 2, the power of the superheater 2 is 3000kw to generate superheated steam with the temperature of 1.2MPa and 300 ℃, the flow rate is about 30t/h, the specific enthalpy value is 3051KJ/kg, the impulse rotation of the steam turbine to 2800 r/min can be realized, the stable maintenance at 2700 r/min can be realized, and finally the non-nuclear impulse rotation of the steam turbine of the high-temperature gas cooled reactor can be realized.

As an alternative embodiment, as shown in fig. 2, a third steam pipeline is further provided between the steam-water separator 3 and the condenser 9. The inlet of each first steam pipeline is respectively provided with a steam-water separator 3 and a first valve 5. The steam generator 1 can also be connected directly to the shaft seal 12 of the steam turbine 11. It should be understood that the above examples are only for clarity of illustration and are not intended to limit the embodiments. Other variations and modifications will be apparent to persons skilled in the art in light of the above description. And are neither required nor exhaustive of all embodiments. And obvious variations or modifications therefrom are within the scope of the utility model.

Claims

1. A high temperature gas cooled reactor non-nuclear steam rush transfer system is characterized by comprising:

the steam generator (1), the superheater (2), the steam-water separator (3) and the main steam pipeline (4) are sequentially communicated along the steam conveying direction, and the main steam pipeline (4) is connected with the mechanism to be flushed.

2. The system according to claim 1, further comprising at least one first branch steam pipeline disposed between the main steam pipeline (4) and the mechanism to be flushed.

3. The system according to claim 2, wherein the first branch steam pipeline is provided with a first valve (5) and at least two second valves (6), and the at least two second valves (6) are connected in parallel.

4. The system according to any one of claims 1 to 3, further comprising a second branch steam pipeline arranged between the main steam pipeline (4) and the mechanism to be flushed, wherein the second branch steam pipeline is connected in parallel with the first branch steam pipeline.

5. The system according to claim 4, wherein a third valve (10) is disposed on the second branch steam pipeline.

6. The system according to claim 5, wherein a condenser (9) is provided between the third valve (10) and the mechanism to be flushed.

7. The non-nuclear steam flushing system of the high temperature gas cooled reactor according to claim 6, wherein a third steam pipeline is further arranged between the steam-water separator (3) and the condenser (9).

8. The system according to any one of claims 1 to 3, wherein the steam generator (1) is an auxiliary electric boiler.