CN210239756U - Steam seal steam supply system of nuclear power unit containing electric heater - Google Patents
Steam seal steam supply system of nuclear power unit containing electric heater Download PDFInfo
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- CN210239756U CN210239756U CN201920869294.XU CN201920869294U CN210239756U CN 210239756 U CN210239756 U CN 210239756U CN 201920869294 U CN201920869294 U CN 201920869294U CN 210239756 U CN210239756 U CN 210239756U
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Abstract
The utility model discloses a steam seal steam supply system of a nuclear power unit containing an electric heater, which comprises a steam supply pipe, a steam seal main pipe, a high-pressure cylinder steam seal, a low-pressure cylinder steam seal, a condenser, a steam supply regulating valve, an overflow regulating valve, a steam seal steam electric heater and a hot standby loop, wherein the steam seal steam electric heater is connected with the inlet end of the steam supply regulating valve; a pressure measuring device is arranged at the inlet side of the steam seal steam electric heater; a temperature measuring device is arranged on the outlet side of the steam seal steam electric heater; the steam seal steam electric heater is internally provided with a controller, a temperature controller and an electric power regulator, and the controller is respectively connected with the pressure measuring device, the temperature measuring device and the temperature controller; one end of the hot standby loop is connected with the steam supply pipe, and the other end of the hot standby loop is connected with the condenser. The utility model discloses a nuclear power generating set contains electric heater's gland steam supply system solves the problem that nuclear power steam turbine gland steam supply temperature superheat degree is not enough.
Description
Technical Field
The utility model relates to a nuclear power unit contains electric heater's vapor seal steam supply system.
Background
The existing steam turbine of the nuclear power unit requires a certain superheat degree of steam supplied by a steam seal, and the steam supplied by the steam seal is not allowed to contain water, but the steam source of the steam seal available for the current nuclear power station is generally wet steam (which is taken from main steam or main steam for pressure reduction), and the steam supply system of the steam seal does not contain an electric heater. The main steam is nearly saturated steam and has no superheat, and even if the main steam throttling is adopted as a steam seal steam source, when the throttling back pressure is high, the condition that the superheat degree of supplied steam is insufficient or has no superheat degree can also occur. In order to ensure that only steam with superheat meeting the requirement can enter a steam seal system, a temperature measuring device is arranged at the upstream of a steam seal steam supply regulating valve, the temperature of the steam seal steam is monitored, and meanwhile, the steam seal steam supply regulating valve is controlled in a linkage mode. When the superheat degree of the steam at the upstream of the steam seal steam supply regulating valve does not meet the requirement, the steam seal steam supply regulating valve is closed in a linkage manner. Although the mode can ensure that the steam superheat degree of the steam supply steam regulating valve meets the steam seal requirement, the problem that a steam seal system cannot work normally when the steam superheat degree in front of the valve does not meet the requirement cannot be solved.
SUMMERY OF THE UTILITY MODEL
The utility model aims at overcoming prior art's defect, provide a nuclear power unit and contain electric heater's gland steam supply system, solve the problem that nuclear power steam turbine gland steam supply vapour temperature superheat degree is not enough, avoided the unit shafting vibration that unqualified gland steam probably leads to, sound bump mill scheduling problem, improved the safety and stability of each operating mode operation of unit.
The technical scheme for realizing the purpose is as follows: the utility model provides a nuclear power unit contains electric heater's gland steam supply system, includes that steam supplies steam pipe, female pipe of gland, high-pressure cylinder gland, low-pressure cylinder gland, condenser, supplies vapour governing valve, overflow governing valve, gland steam electric heater and hot reserve circuit, wherein:
the steam supply pipe is respectively connected with the high-pressure cylinder steam seal, the low-pressure cylinder steam seal and the condenser through the steam seal main pipe;
the steam supply regulating valve is arranged on the steam supply pipe;
the overflow regulating valve is arranged on the steam seal main pipe;
the steam seal steam electric heater is connected with the inlet end of the steam supply regulating valve;
a pressure measuring device is arranged at the inlet side of the steam seal steam electric heater;
the outlet side of the steam seal steam electric heater is provided with a temperature measuring device, and the temperature measuring device is positioned between the steam seal steam electric heater and the inlet end of the steam supply regulating valve;
the steam seal steam electric heater is internally provided with a controller, a temperature controller and an electric power regulator, the controller is respectively connected with the pressure measuring device, the temperature measuring device and the temperature controller, and the electric power regulator is respectively connected with the steam seal steam electric heater and the temperature controller;
one end of the hot standby loop is connected with the steam supply pipe, the other end of the hot standby loop is connected with the condenser, and the connecting end of the hot standby loop and the steam supply pipe is positioned between the temperature measuring device and the inlet end of the steam supply regulating valve.
The steam seal steam supply system of the nuclear power unit with the electric heater comprises a condenser and a steam outlet pipe.
The steam seal steam supply system of the nuclear power unit with the electric heater comprises a hot standby loop and a hot standby loop, wherein the hot standby loop is provided with a throttling orifice plate and/or a drain valve.
The utility model discloses a nuclear power unit contains electric heater's gland steam supply system solves the problem that nuclear power steam turbine gland steam supply vapour temperature superheat degree is not enough, has avoided the unit shafting vibration that unqualified gland steam probably leads to, sound bump grinding scheduling problem, has improved the safety and stability of each operating mode operation of unit, specifically embodies:
(1) by arranging the steam seal steam electric heater, the steam seal steam supply temperature is effectively regulated, the problem of insufficient superheat degree of the steam seal steam supply temperature is solved, the problems of machine set shafting vibration, dynamic and static rubbing and the like possibly caused by unqualified steam seal steam are avoided, and the safety and stability of the machine set in each working condition operation are improved;
(2) the accurate logic control of the steam supply temperature of the steam seal is realized by arranging a pressure measuring device at the inlet of the steam electric heater of the steam seal, arranging a temperature measuring device at the outlet of the steam electric heater of the steam seal, and arranging a built-in controller (PLC), a temperature controller (TIC) and a power regulator (SCR), so that the heating power required under partial pressure conditions is reduced, the size of electric heater equipment is further reduced, the arrangement of a power plant is facilitated, and the economy is improved;
(3) through setting up hot standby loop all the way, guaranteed that the unit is under load shedding, sudden operating mode such as trip, electrical heating can be put into operation fast, heats steam to required temperature rapidly.
Drawings
FIG. 1 is a structural diagram of a steam seal steam supply system of a nuclear power unit containing an electric heater of the utility model;
FIG. 2 is a schematic diagram of the operation of the controller of the gland seal steam electric heater;
fig. 3 is a working schematic diagram of the steam seal steam supply system of the nuclear power unit containing the electric heater.
Detailed Description
In order to make the technical solution of the present invention better understood by those skilled in the art, the following detailed description is provided with reference to the accompanying drawings:
referring to fig. 1, 2 and 3, a steam seal steam supply system of a nuclear power plant including an electric heater according to a preferred embodiment of the present invention includes a steam supply pipe 1, a steam seal main pipe 2, a high pressure cylinder steam seal 3, a low pressure cylinder steam seal 4, a condenser 5, a steam supply regulating valve 6, an overflow regulating valve 7, a steam seal electric steam heater 8 and a hot standby loop 9. The condenser 5 may be replaced by a hydrophobic flash tank.
The steam supply pipe 1 is respectively connected with a high-pressure cylinder steam seal 3, a low-pressure cylinder steam seal 4 and a condenser 5 through a steam seal main pipe 2; the steam supply regulating valve 6 is arranged on the steam supply pipe 1; the overflow regulating valve 7 is arranged on the steam seal main pipe 2; the steam seal steam electric heater 8 is connected with the inlet end of the steam supply regulating valve 6; the inlet side of the steam seal electric steam heater 8 is provided with a pressure measuring device PT; the outlet side of the steam seal steam electric heater 8 is provided with a temperature measuring device TT, and the temperature measuring device TT is positioned between the steam seal steam electric heater 8 and the inlet end of the steam supply regulating valve.
The electric steam-sealing steam heater 8 is internally provided with a controller (PLC)81, a temperature controller (TIC)82 and an electric power regulator (SCR)83, the controller 81 is respectively connected with a pressure measuring device PT, a temperature measuring device TT and the temperature controller 82, and the electric power regulator 83 is respectively connected with the electric steam-sealing steam heater 8 and the temperature controller 82. The output power of the steam seal steam electric heater is adjusted through a controller 81, a temperature controller 82 and an electric power adjuster 83 which are arranged in the steam seal steam electric heater, so that the actual value (PV value) of the outlet temperature of the steam seal steam electric heater is consistent with the set value (SV value), and finally, the superheat degree of the steam seal steam supply temperature is accurately realized to meet the temperature requirement of the design of a steam seal steam supply system.
One end of the hot standby loop 9 is connected with the steam supply pipe 1, the other end of the hot standby loop is connected with the condenser 5, and the connection end a of the hot standby loop 9 and the steam supply pipe 1 is positioned between the temperature measuring device TT and the inlet end of the steam supply regulating valve 6. The hot standby circuit 9 is provided with a throttle orifice 91 and/or a drain valve 92, namely the hot standby circuit 9 is provided with the drain valve 92 or the throttle orifice 91 or the combination of the two to lead to the condenser 5.
In the steam seal steam supply system of the nuclear power unit containing the electric heater, the number of the low-pressure cylinder steam seals 4 is not limited to one, and can be two or more; the number of the high-pressure cylinder steam seal 3 is not limited, and the high-pressure cylinder steam seal can be a single cylinder or double cylinders; the configuration of the hot standby circuit 9 is not limited to one, and may be an orifice plate or a drain valve or a combination of the two; the configuration modes of the steam supply valve station and the overflow valve station are not limited, and valves can be additionally arranged in front of and behind the steam supply regulating valve and the overflow regulating valve and on the bypass; the logic control mode and configuration mode of the controller 81 are not limited, and the power regulator 83 may be disposed at the inlet of the electric steam seal heater 8 or at the outlet of the electric steam seal heater 8.
Referring to fig. 3 again, the steam seal steam supply system of the nuclear power generating unit with the electric heater of the present invention sets the steam seal steam electric heater 8 before the steam supply regulating valve 6, and realizes the automatic accurate control of the steam seal steam supply temperature by setting the pressure measuring device PT on the inlet side of the steam seal steam electric heater 8, setting the temperature measuring device TT on the outlet side, and setting the controller (PLC)81, the temperature controller (TIC)82 and the power regulator (SCR)83 in the steam seal steam supply system. Meanwhile, a hot standby loop 9 is additionally arranged between the steam seal electric steam heater 8 and the steam seal steam supply regulating valve 6, steam is led to the condenser 5 or the drainage flash tank, trace steam is kept to pass through, the electric heater is still in a warm standby state when the unit is in a self-sealing state, and therefore under sudden working conditions such as load shedding and trip of the unit, the electric heater can be rapidly put into operation to rapidly heat the steam to required temperature.
To sum up, the utility model discloses a nuclear power unit contains electric heater's gland steam supply system solves the not enough problem of nuclear power steam turbine gland steam supply temperature superheat degree, has avoided the unit shafting vibration that unqualified gland steam probably leads to, sound bump grinding scheduling problem, has improved the safety and stability of each operating mode operation of unit.
It will be appreciated by those skilled in the art that the above embodiments are only for illustrating the present invention and are not to be used as limitations of the present invention, and that changes and modifications to the above described embodiments will fall within the scope of the claims of the present invention as long as they are within the spirit and scope of the present invention.
Claims (3)
1. The utility model provides a nuclear power unit contains electric heater's gland steam supply system which characterized in that, supplies steam pipe, female pipe of gland, high-pressure cylinder gland, low-pressure cylinder gland, condenser, supplies vapour governing valve, overflow governing valve, gland steam electric heater and heat reserve circuit including steam, wherein:
the steam supply pipe is respectively connected with the high-pressure cylinder steam seal, the low-pressure cylinder steam seal and the condenser through the steam seal main pipe;
the steam supply regulating valve is arranged on the steam supply pipe;
the overflow regulating valve is arranged on the steam seal main pipe;
the steam seal steam electric heater is connected with the inlet end of the steam supply regulating valve;
a pressure measuring device is arranged at the inlet side of the steam seal steam electric heater;
the outlet side of the steam seal steam electric heater is provided with a temperature measuring device, and the temperature measuring device is positioned between the steam seal steam electric heater and the inlet end of the steam supply regulating valve;
the steam seal steam electric heater is internally provided with a controller, a temperature controller and an electric power regulator, the controller is respectively connected with the pressure measuring device, the temperature measuring device and the temperature controller, and the electric power regulator is respectively connected with the steam seal steam electric heater and the temperature controller;
one end of the hot standby loop is connected with the steam supply pipe, the other end of the hot standby loop is connected with the condenser, and the connecting end of the hot standby loop and the steam supply pipe is positioned between the temperature measuring device and the inlet end of the steam supply regulating valve.
2. The steam seal steam supply system of the nuclear power generating unit containing the electric heater as claimed in claim 1, wherein the condenser is replaced with a hydrophobic flash tank.
3. The steam seal steam supply system of the nuclear power generating unit containing the electric heater as claimed in claim 1, wherein a throttle orifice and/or a drain valve is provided on the hot standby loop.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920869294.XU CN210239756U (en) | 2019-06-11 | 2019-06-11 | Steam seal steam supply system of nuclear power unit containing electric heater |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920869294.XU CN210239756U (en) | 2019-06-11 | 2019-06-11 | Steam seal steam supply system of nuclear power unit containing electric heater |
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| Publication Number | Publication Date |
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| CN210239756U true CN210239756U (en) | 2020-04-03 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201920869294.XU Active CN210239756U (en) | 2019-06-11 | 2019-06-11 | Steam seal steam supply system of nuclear power unit containing electric heater |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114575943A (en) * | 2022-03-30 | 2022-06-03 | 西安热工研究院有限公司 | Control system and method for shaft seal electric heater of shaft seal system of ultra-supercritical unit |
-
2019
- 2019-06-11 CN CN201920869294.XU patent/CN210239756U/en active Active
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114575943A (en) * | 2022-03-30 | 2022-06-03 | 西安热工研究院有限公司 | Control system and method for shaft seal electric heater of shaft seal system of ultra-supercritical unit |
| CN114575943B (en) * | 2022-03-30 | 2024-03-12 | 西安热工研究院有限公司 | Shaft seal electric heater control system and method for shaft seal system of ultra-supercritical unit |
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