CN217544174U - High-temperature reactor water supply system - Google Patents
High-temperature reactor water supply system Download PDFInfo
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- CN217544174U CN217544174U CN202221627402.0U CN202221627402U CN217544174U CN 217544174 U CN217544174 U CN 217544174U CN 202221627402 U CN202221627402 U CN 202221627402U CN 217544174 U CN217544174 U CN 217544174U
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Abstract
The utility model provides a high-temperature reactor water supply system, which comprises a first running water supply pump, a first pipeline, a first steam generator, a standby water pump and a second pipeline; the first pipeline is connected with the first steam generator; the first running feed water pump is arranged on the first pipeline and used for pumping the feed water of the second loop to the first steam generator; the second pipeline is connected with the first steam generator; the standby water pump is arranged in the second pipeline; and the liquid coupling opening degree of the standby water pump as the heat standby is the same as that of the first operation water supply pump. The utility model has the technical effects that the structure design is reasonable, the reactor can be cooled in time, the shutdown of the reactor caused by the over-limit of the helium water flow ratio is avoided, and the stability of the steam flow is ensured; meanwhile, the high-temperature reactor water supply system can avoid the reverse pressure bearing of the heat transfer pipe of the steam generator.
Description
Technical Field
The utility model belongs to the technical field of the nuclear power, concretely relates to high temperature reactor water supply system.
Background
And the two loops of feed water of the high-temperature reactor are boosted by a feed pump and then supplied to a steam generator. Through the heat exchange of the steam generator, the two loops of feed water carry out the heat generated by the primary loop reactor, and meanwhile, the temperature of the two loops of feed water is increased and converted into steam so as to push the steam turbine generator set to generate electric energy.
The existing standby water feeding pump is in a public cold standby state, and when the operation water feeding pump stops, the standby water feeding pump needs to be manually switched to recover water supply of the steam generator.
However, in this operation mode, if the operation water-feeding pump is unexpectedly stopped, the pressure and flow rate of the two-loop water-feeding will be reduced to zero within the preset time, and the operation water-feeding pump is manually switched to the standby water-feeding pump, the switching process is long, and the pressure and flow rate of the two-loop water-feeding cannot be recovered within the preset time, thereby leading to the following technical problems:
1. the reactor loses cooling and the helium water flow ratio is exceeded resulting in reactor shutdown.
2. The heat transfer tubes of the steam generator are reversely pressurized. Multiple reverse pressure bearing of the heat transfer pipe easily causes cracks at the joint position of the heat transfer pipe, and further causes the penetration of a primary loop and a secondary loop, so that serious consequences such as reactor water feeding and radioactivity of secondary loop water supply occur.
3. The steam flow reduces, triggers turbo generator set load shedding, causes the disturbance to turbo generator set, reduces the economic nature of power plant.
SUMMERY OF THE UTILITY MODEL
The utility model discloses aim at solving one of the technical problem that exists among the prior art at least, provide a high temperature reactor water supply system's new technical scheme.
According to an aspect of the utility model, a high temperature reactor water supply system is provided, include:
the system comprises a first running feed water pump, a first pipeline and a first steam generator, wherein the first pipeline is connected with the first steam generator; the first running feed water pump is arranged on the first pipeline and used for pumping the feed water of the second loop to the first steam generator;
the standby water pump and the second pipeline are connected with the first steam generator; the standby water pump is arranged in the second pipeline and used for pumping secondary loop feed water to the first steam generator when the first running feed water pump is stopped;
and the liquid coupling opening degree of the standby water pump as a heat standby is the same as that of the first running water feed pump.
Optionally, the high-temperature reactor feedwater system further comprises:
the system comprises a first running feed water pump, a first pipeline and a first steam generator, wherein the first pipeline is connected with the first steam generator; the second running feed water pump is arranged on the third pipeline and used for pumping the second loop feed water to the second steam generator;
the first branch pipe and the second branch pipe are connected, one end of the first branch pipe is connected with the second pipeline, and the other end of the first branch pipe is connected with the first steam generator; one end of the second branch pipe is connected with the second pipeline, and the other end of the second branch pipe is connected with the second steam generator;
the standby water pump is also used for pumping secondary loop water supply to the second steam generator when the second running water supply pump is stopped.
Optionally, the high-temperature reactor feedwater system further comprises:
the first button is connected between the standby water pump and the first steam generator and used for manually selecting the standby water pump as a first running water feeding pump for hot standby, and the first running pump is automatically started to pump a second loop to feed water to the first steam generator after being unexpectedly stopped;
and the second button is connected between the standby water pump and the second steam generator, and the second button is used for manually selecting the standby water pump as a second operation water feed pump for heat standby, and automatically starts to pump a second loop of water to the second steam generator after the second operation pump is accidentally stopped.
Optionally, the high temperature reactor feedwater system further comprises:
the first display lamp is electrically connected with the standby water pump, and is turned on when the first power supply of the standby water pump is selected and sent to a working position;
and the second display lamp is electrically connected with the standby water pump, and is turned on when a second power supply of the standby water pump is selected and sent to a working position.
Optionally, the high-temperature reactor feedwater system further comprises:
the first electric valve is arranged on the first branch pipe and used for controlling the opening or closing of the first branch pipe;
and the second electric valve is arranged on the second branch pipe and is used for controlling the opening or closing of the second branch pipe.
Optionally, the high-temperature reactor feedwater system further comprises:
a first fluid coupling connected to the first running feedwater pump;
the second hydraulic coupler is connected with the standby water pump;
a third fluid coupling connected to the second operating feed pump;
when the standby water pump is used as the first running water-feeding pump for heat standby, the opening of the scoop tube of the second hydraulic coupler automatically tracks the opening of the scoop tube of the first hydraulic coupler;
when the standby water pump is used as the second running water feeding pump for heat standby, the opening degree of the scoop tube of the second hydraulic coupler automatically tracks the opening degree of the scoop tube of the first hydraulic coupler.
Optionally, the high-temperature reactor feedwater system further comprises:
the end, far away from the first steam generator, of the first pipeline is connected with the deaerator; and one end of the third pipeline, which is far away from the second steam generator, is connected with the deaerator.
Optionally, the high-temperature reactor feedwater system further comprises:
the first circulating pipe is connected with the deaerator at one end and connected with a first pipeline at the other end; the first recirculation valve is disposed on the first recirculation pipe;
the device comprises a first recirculation valve, a first circulation pipe and a second circulation pipe, wherein one end of the first circulation pipe is connected with the deaerator, and the other end of the first circulation pipe is connected with a first pipeline; the second recirculation valve is disposed on the second circulation pipe;
one end of the third circulating pipe is connected with the deaerator, and the other end of the third circulating pipe is connected with a third pipeline; the third recirculation valve is disposed on the third circulation pipe.
Optionally, the high-temperature reactor feedwater system further comprises:
the third electric valve is arranged on the first pipeline and used for controlling the opening or closing of the first pipeline;
and the fourth electric valve is arranged on the third pipeline and used for controlling the opening or closing of the third pipeline.
Optionally, the high-temperature reactor feedwater system further comprises:
the first inlet isolation valve is arranged on the first pipeline and is positioned between the deaerator and the first running water feed pump;
a second inlet isolation valve disposed in the third pipe and between the deaerator and the second running feed pump;
and the third inlet isolating valve is arranged on the second pipeline and is positioned between the deaerator and the standby water pump.
The utility model has the technical effects that:
in the embodiment of the application, the liquid coupling opening degree of the standby water pump used as the heat standby is automatically followed by the liquid coupling opening degree of the first operation water feeding pump, so that after the first operation water feeding pump is tripped accidentally, the standby water pump can be started in time and pumps the first steam generator for supplying water to the second loop, a reactor can be cooled in time, the shutdown of the reactor caused by the over-limit of the helium water flow ratio is avoided, and the stability of the steam flow is ensured; meanwhile, the high-temperature reactor water supply system can avoid the reverse pressure bearing of the heat transfer pipe of the steam generator.
Drawings
Fig. 1 is a schematic structural diagram of a high temperature reactor feedwater system according to an embodiment of the present invention.
In the figure: 11. a first operating feed pump; 12. a first conduit; 13. a first steam generator; 14. a first recirculation valve; 15. a first circulation pipe; 16. a first inlet isolation valve; 21. a standby water pump; 22. a second conduit; 221. a first branch pipe; 222. a second branch pipe; 23. a second recirculation valve; 24. a second circulation pipe; 25. a second inlet isolation valve; 31. a second running feed pump; 32. a third pipeline; 33. a second steam generator; 34. a third recirculation valve; 35. a third circulation pipe; 36. a third inlet isolation valve; 41. a first electrically operated valve; 42. a second electrically operated valve; 43. a third electrically operated valve; 44. a fourth electrically operated valve; 51. a first fluid coupling; 52. a second hydraulic coupler; 53. a third fluid coupling; 6. a deaerator.
Detailed Description
Various exemplary embodiments of the present application will now be described in detail with reference to the accompanying drawings. It should be noted that: the relative arrangement of the components and steps, the numerical expressions, and numerical values set forth in these embodiments do not limit the scope of the present application unless specifically stated otherwise.
Reference will now be made in detail to the embodiments of the present application, examples of which are illustrated in the accompanying drawings, wherein like reference numerals refer to the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference 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 obtained by a person of ordinary skill in the art based on the embodiments in the present application without making any creative effort belong to the protection scope of the present application.
The features of the terms first and second in the description and in the claims of the present application may explicitly or implicitly include one or more of such features. In the description of the present application, "a plurality" means two or more unless otherwise specified. In addition, "and/or" in the specification and claims means at least one of connected objects, a character "/" generally means that a preceding and succeeding related objects are in an "or" relationship.
In the description of the present application, it is to be understood that the terms "central," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," "circumferential," and the like are used in the orientations and positional relationships indicated in the drawings for convenience in describing the present application and to simplify the description, and are not intended to indicate or imply that the referenced devices or elements must have a particular orientation, be constructed and operated in a particular orientation, and are therefore not to be considered limiting of the present application.
In the description of the present application, it is to be noted that, unless otherwise explicitly specified or limited, the terms "mounted," "connected," and "connected" are to be construed broadly, e.g., as meaning either a fixed connection, a removable connection, or an integral connection; can be mechanically or electrically connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. The specific meaning of the above terms in this application will be understood to be a specific case for those of ordinary skill in the art.
As shown in FIG. 1, the embodiment of the application provides a high-temperature stack feedwater system, which comprises a first running feedwater pump 11, a first pipeline 12, a first steam generator 13, a standby water pump 21 and a second pipeline 22.
Specifically, the first pipe 12 is connected with the first steam generator 13; the first running feed water pump 11 is disposed in the first pipe 12 and is configured to pump a second loop of feed water to the first steam generator 13.
Further specifically, the second pipe 22 is connected with the first steam generator 13; the backup water pump 21 is disposed in the second pipe 22 and is used to pump the second loop feedwater to the first steam generator 13 when the first running feedwater pump 11 is not running.
The liquid coupling opening degree of the standby water pump 21 as the hot standby is the same as that of the first operation water supply pump 11, that is, the liquid coupling opening degree of the standby water pump 21 as the hot standby automatically follows the liquid coupling opening degree of the first operation water supply pump 11.
In the embodiment of the present application, the liquid coupling opening of the backup water pump 21 for heat backup is the same as the liquid coupling opening of the first operating feed water pump 11, that is, the liquid coupling opening of the backup water pump 21 for heat backup can automatically follow the liquid coupling opening of the second operating feed water pump 21, so that after the first operating feed water pump 11 trips accidentally, the backup water pump 21 can be started in time and can pump two loops of feed water for the first steam generator 13, which not only enables the reactor to be cooled in time, avoids the shutdown of the reactor caused by the over-limit of the helium water flow ratio, but also ensures the stability of the steam flow; meanwhile, the high-temperature reactor water supply system can prevent the heat transfer pipe of the steam generator from bearing pressure reversely.
Optionally, the high temperature reactor feedwater system further comprises:
a second running feedwater pump 31, a third conduit 32, and a second steam generator 33, said third conduit 32 being connected to said second steam generator 33; the second running feed water pump 31 is disposed in the third pipe 32, and is used for pumping a second loop feed water to the second steam generator 33;
a first branch pipe 221 and a second branch pipe 222, one end of the first branch pipe 221 being connected to the second pipe 22, and the other end being connected to the first steam generator 13; one end of the second branch pipe 222 is connected to the second pipe 22, and the other end is connected to the second steam generator 33;
the backup water pump 21 is also used to pump a secondary loop of feedwater to the second steam generator 33 when the second run feedwater pump 31 is off.
In the above embodiment, when the backup water pump 21 is thermally backup for the first running water feed pump 11 or the second running water feed pump 31, the fluid coupling opening degree of the backup water pump 21 can automatically follow the fluid coupling opening degree of the first running water feed pump 11 or the second running water feed pump 31 within ± 0.05%. Therefore, after the first running water-feeding pump 11 or the second running water-feeding pump 31 stops running, the standby water pump 21 can rapidly and stably reach the rotating speed, the flow rate and the pressure corresponding to the liquid coupling opening degree before the first running water-feeding pump 11 or the second running water-feeding pump 31 stops running within the preset time, the reactor is not stopped, the heat transfer pipe of the steam generator is not subjected to reverse pressure bearing, the load of the steam turbine generator unit is not obviously reduced, and the power generation efficiency of the steam turbine generator unit is ensured.
After the backup water pump 21 is started, the fluid coupling opening degree of the backup water pump 21 does not follow the fluid coupling opening degree of the first running water feed pump 11 or the second running water feed pump 31, but operates according to the fluid coupling opening degree requirement of the backup water pump 21 itself.
Optionally, the high-temperature reactor feedwater system further comprises:
the first button is connected between the standby water pump 21 and the first steam generator 13 and used for manually selecting the standby water as the hot standby water of the first running water-feeding pump 11, and the first button automatically starts to pump a second loop of water feeding to the first steam generator 13 after the first running water-feeding pump 11 is accidentally stopped;
and a second button, wherein a second button is connected between the standby water pump 21 and the second steam generator 33, the second button is used for manually selecting the standby water pump 21 as a second operation water feed pump 31 for hot standby, and the second operation water feed pump 31 is automatically started to feed water to a second loop pumped by the second steam generator 33 after being accidentally stopped.
In the above embodiment, the first button (not shown) allows the operator to manually switch the use state of the backup water pump 21, such as pumping the secondary loop feed water to the first steam generator 13 or stopping pumping the secondary loop feed water to the first steam generator 13; the second button (not shown in the figure) can be used for manually switching the use state of the standby water pump 21 by an operator, for example, the second steam generator 33 is pumped with the secondary loop water supply or the pumping of the secondary loop water supply to the second steam generator 33 is stopped, so that the use flexibility is good, and the operation is simple.
Optionally, the high-temperature reactor feedwater system further comprises:
a first display lamp (not shown in the figure), which is electrically connected with the standby water pump 21 and is turned on when the first power supply of the standby water pump is selected to be sent to a working position; reminding an operator, and selecting the standby water pump as a first running water feed pump to pump a second loop of feed water to the first steam generator;
and the second display lamp (not shown in the figure) is electrically connected with the standby water pump 21, and is turned on to remind an operator when the second power supply of the standby water pump is selected to be sent to a working position, so that the standby water pump can be selected as a second running water feeding pump for heat standby.
In the above embodiment, the first and second display lamps can be displayed to the operator to make the operator know the working status of the backup water pump 21 more clearly, such as not working, pumping the second loop feedwater for the first steam generator 13 instead of the first running feedwater pump 11, or pumping the second loop feedwater for the second steam generator 33 instead of the second running feedwater pump 31.
It should be noted that, a first display lamp, a second display lamp, a first button and a second button are added to a picture of a DCS (Distributed Control System) main water supply System to realize Control of the high temperature reactor water supply System, and the operation is simple.
Optionally, the high temperature reactor feedwater system further comprises:
a first electric valve 41, wherein the first electric valve 41 is disposed in the first branch pipe 221 and is used for controlling the opening or closing of the first branch pipe 221;
a second electric valve 42, wherein the second electric valve 42 is disposed in the second branch pipe 222 for controlling the opening or closing of the second branch pipe 222.
In the above embodiment, whether the backup water pump 21 supplies water to the first steam generator 13 or not can be controlled by the first electric valve 41, and whether the backup water pump 21 supplies water to the second steam generator 33 or not can be controlled by the second electric valve 42.
Optionally, the high-temperature reactor feedwater system further comprises:
a first fluid coupling 51, said first fluid coupling 51 being connected to said first running feedwater pump 11;
a second hydraulic coupler 52, wherein the second hydraulic coupler 52 is connected with the backup water pump 21;
a third fluid coupling 53, wherein the third fluid coupling 53 is connected to the second running feed pump 31;
it should be noted that the hydraulic coupler is controlled by the flow demand of the steam generator inlet, and the larger the flow demand is, the larger the opening of the scoop tube of the hydraulic coupler is, and the higher the rotation speed of the feed pump is, the larger the flow is provided.
When the standby water pump 21 is used as a hot standby, the scoop tube opening of the second hydraulic coupler 52 automatically tracks the scoop tube opening of the first hydraulic coupler 51 or the scoop tube opening of the third hydraulic coupler 53.
For example, when the standby water pump is used as the first running water-feeding pump for heat standby, the opening degree of the scoop tube of the second hydraulic coupler automatically tracks the opening degree of the scoop tube of the first hydraulic coupler, so that when the first running water-feeding pump is stopped running and the standby water pump is started, the water supply pressure and flow can be quickly recovered, and the tracking of the opening degree of the scoop tube can be automatically stopped after the first running pump is stopped running, so that the standby water pump can change the position of the scoop tube according to the state requirement of the first steam generator.
And when the standby water pump is used as the second operation water feed pump for heat standby, the opening degree of the scoop tube of the second hydraulic coupler automatically tracks the opening degree of the scoop tube of the first hydraulic coupler, so that when the second operation water feed pump stops running and the standby water pump is started, the water supply pressure and flow are quickly recovered, and the tracking of the opening degree of the scoop tube is automatically stopped after the first operation pump stops running, so that the standby water pump can change the position of the scoop tube according to the state requirement of the second steam generator.
In the above embodiment, the fluid coupling opening degree of the first-operation feed water pump 11 can be preferably controlled by the first fluid coupling 51; the hydraulic coupling opening degree of the backup water pump 21 can be well controlled through the second hydraulic coupler 52; the fluid coupling opening of the second operating feed water pump 31 can be controlled better by the third fluid coupling 53. When helping realizing that reserve water pump 21 is as hot standby, reserve water pump 21's liquid coupling aperture can accurately follow first operation feed water pump 11 or second operation feed water pump 31's liquid coupling aperture, make first operation feed water pump 11 or second operation feed water pump 31 after the shut down, reserve water pump 21 can be stabilized the rotational speed that first operation feed water pump 11 or second operation feed water pump 31 before the shut down corresponds, flow and pressure fast in the time of predetermineeing, thereby can cool off the reactor well, the stability of high temperature reactor operation process has been guaranteed.
When the backup water pump 21 is used as a hot backup, the first electric valve 41 or the second electric valve 42 needs to be opened. Therefore, after the standby water pump 21 is started, the standby water pump can be timely merged into a system to recover water supply, and the phenomenon that the helium water flow ratio exceeds the limit to cause reactor shutdown and reverse pressure bearing of a heat transfer pipe of a steam generator due to excessive reduction of the water supply flow and the pressure is avoided.
Optionally, the high temperature reactor feedwater system further comprises:
the deaerator 6 is connected with one end, far away from the first steam generator 13, of the first pipeline 12; the end of the third pipe 32 far from the second steam generator 33 is connected with the deaerator 6. The deaerator is responsible for providing a water supply and an operating head for the first operating feed water pump, the second operating feed water pump and the standby water pump, and receiving the recirculation flow.
In the above embodiment, the deaerator 6 is used to remove oxygen and other gases in the two-loop feed water, so as to ensure the quality of the two-loop feed water and prevent the relevant pipelines from being oxidized by the equipment.
Optionally, the high-temperature reactor feedwater system further comprises:
a first recirculation valve 14 and a first recirculation pipe 15, said first recirculation pipe 15 being connected at one end to said deaerator 6 and at the other end to a first pipe 12; said first recirculation valve 14 is arranged on said first recirculation pipe 15;
a second recirculation valve 23 and a second circulation pipe 24, one end of the second circulation pipe 24 being connected to the deaerator 6 and the other end being connected to the second pipe 22; the second recirculation valve 23 is disposed on the second circulation pipe 24;
a third recirculation valve 34 and a third recirculation pipe 35, one end of the third recirculation pipe 35 being connected to the deaerator 6, and the other end being connected to the third pipe 32; the third recirculation valve 34 is provided to the third circulation pipe 35.
The recirculation pipeline is used for providing minimum operation flow for the first operation water feed pump, the second operation water feed pump and the standby water pump and preventing the first operation water feed pump, the second operation water feed pump and the standby water pump from generating cavitation.
In the above embodiment, the first recirculation valve 14 and the first recirculation pipe 15 can well protect the safe operation of the first operational feedwater pump 11; the second recirculation valve 23 and the second recirculation pipe 24 can better protect the safe operation of the backup water pump 21; the third recirculation valve 34 and the third recirculation pipe 35 can better protect the safe operation of the second operational feedwater pump 31.
Optionally, the high-temperature reactor feedwater system further comprises:
a third electric valve 43, wherein the third electric valve 43 is disposed in the first pipe 12 and is used for controlling the opening or closing of the first pipe 12;
a fourth electric valve 44, wherein the fourth electric valve 44 is disposed in the third duct 32 for controlling the opening or closing of the third duct 32.
In the above embodiment, whether the first operation feed water pump 11 supplies water to the first steam generator 13 or not can be controlled by the third electric valve 43, and whether the second operation feed water pump 31 supplies water to the second steam generator 33 or not can be controlled by the fourth electric valve 44, so that the operation is simple and the control is easy.
Optionally, the high temperature reactor feedwater system further comprises:
a first inlet isolation valve 16, wherein the first inlet isolation valve 16 is arranged on the first pipeline 12 and is positioned between the deaerator 6 and the first running feed water pump 11;
a second inlet isolation valve 25, wherein the second inlet isolation valve 25 is arranged on the third pipeline 32 and is positioned between the deaerator 6 and the second running water feed pump 31;
and a third inlet isolation valve 36, wherein the third inlet isolation valve 36 is arranged on the second pipeline 22 and is positioned between the deaerator 6 and the standby water pump 21.
The first inlet isolation valve 16, the second inlet isolation valve 25, and the third inlet isolation valve 36 are all in an open state except for pump maintenance isolation, so manual valves are used.
In the above embodiment, the first inlet isolation valve 16 can control whether the deaerator 6 supplies water to the first pipe 12; the second inlet isolation valve 25 is able to control whether the deaerator 6 supplies water to the third pipe 32; the third inlet isolation valve 36 can control whether the deaerator 6 supplies water to the second pipeline 22, and the operation is simple.
When the first running water feed pump 11 or the second running water feed pump 31 is tripped, the standby water pump 21 is automatically started in an interlocking manner, and the speed is rapidly increased to the rotating speed, the flow and the pressure corresponding to the liquid coupling opening degree before the first running water feed pump 11 or the second running water feed pump 31 is stopped, so that the reactor shutdown and the reverse pressure bearing of the steam generator are prevented from being triggered.
It is to be understood that the above embodiments are merely exemplary embodiments that have been employed to illustrate the principles of the present invention, and that the present invention is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.
Claims (10)
1. A high temperature reactor feedwater system, comprising:
the system comprises a first running feed water pump, a first pipeline and a first steam generator, wherein the first pipeline is connected with the first steam generator; the first running feed water pump is arranged on the first pipeline and used for pumping the feed water of the second loop to the first steam generator;
the standby water pump and the second pipeline are connected with the first steam generator; the standby water pump is arranged in the second pipeline and used for pumping secondary loop feed water to the first steam generator when the first running feed water pump is stopped;
and the liquid coupling opening degree of the standby water pump as the heat standby is the same as that of the first operation water supply pump.
2. The thermopile feedwater system of claim 1, further comprising:
the system comprises a first running feed water pump, a first pipeline and a first steam generator, wherein the first pipeline is connected with the first steam generator; the second running feed water pump is arranged on the third pipeline and used for pumping the second loop feed water to the second steam generator;
the first branch pipe and the second branch pipe are connected, one end of the first branch pipe is connected with the second pipeline, and the other end of the first branch pipe is connected with the first steam generator; one end of the second branch pipe is connected with the second pipeline, and the other end of the second branch pipe is connected with the second steam generator;
the standby water pump is also used for pumping secondary loop water supply to the second steam generator when the second running water supply pump is stopped.
3. The high temperature reactor feedwater system of claim 2, further comprising:
the first button is connected between the standby water pump and the first steam generator and used for manually selecting the standby water pump as a first running water feeding pump for hot standby, and the first running pump is automatically started to pump a second loop to feed water to the first steam generator after being unexpectedly stopped;
the second button, the standby water pump with be connected with the second button between the second steam generator, the second button is used for the manual selection standby water pump is as second operation feed water pump heat reserve, after the unexpected stop of second operation pump automatic start to second steam generator pump delivery secondary circuit is for water.
4. The high temperature reactor feedwater system of claim 2, further comprising:
the first display lamp is electrically connected with the standby water pump, and is turned on when the first power supply of the standby water pump is selected and sent to a working position;
and the second display lamp is electrically connected with the standby water pump, and is turned on when a second power supply of the standby water pump is selected and sent to a working position.
5. The high temperature reactor feedwater system of claim 2, further comprising:
the first electric valve is arranged on the first branch pipe and used for controlling the opening or closing of the first branch pipe;
and the second electric valve is arranged on the second branch pipe and is used for controlling the opening or closing of the second branch pipe.
6. The thermopile feedwater system of claim 5, further comprising:
a first fluid coupling connected to the first running feedwater pump;
the second hydraulic coupler is connected with the standby water pump;
a third fluid coupling connected to the second operating feed pump;
when the standby water pump is used as the first running water-feeding pump for heat standby, the opening of the scoop tube of the second hydraulic coupler automatically tracks the opening of the scoop tube of the first hydraulic coupler;
when the standby water pump is used as the second running water feeding pump for heat standby, the opening degree of the scoop tube of the second hydraulic coupler automatically tracks the opening degree of the scoop tube of the first hydraulic coupler.
7. The thermopile feedwater system of claim 6, further comprising:
the end, far away from the first steam generator, of the first pipeline is connected with the deaerator; and one end of the third pipeline, which is far away from the second steam generator, is connected with the deaerator.
8. The thermopile feedwater system of claim 7, further comprising:
the first circulating pipe is connected with the deaerator at one end and connected with a first pipeline at the other end; the first recirculation valve is disposed at the first recirculation pipe;
the device comprises a first recirculation valve, a first circulation pipe and a second circulation pipe, wherein one end of the first circulation pipe is connected with the deaerator, and the other end of the first circulation pipe is connected with a first pipeline; the second recirculation valve is disposed on the second circulation pipe;
one end of the third circulating pipe is connected with the deaerator, and the other end of the third circulating pipe is connected with a third pipeline; the third recirculation valve is disposed on the third circulation pipe.
9. The thermopile feedwater system of claim 8, further comprising:
the third electric valve is arranged on the first pipeline and used for controlling the opening or closing of the first pipeline;
and the fourth electric valve is arranged on the third pipeline and used for controlling the opening or closing of the third pipeline.
10. The thermopile feedwater system of claim 7, further comprising:
the first inlet isolation valve is arranged on the first pipeline and is positioned between the deaerator and the first running water feed pump;
the second inlet isolation valve is arranged on the third pipeline and is positioned between the deaerator and the second running water feed pump;
and the third inlet isolating valve is arranged on the second pipeline and is positioned between the deaerator and the standby water pump.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202221627402.0U CN217544174U (en) | 2022-06-27 | 2022-06-27 | High-temperature reactor water supply system |
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