CN206572497U - A kind of system for heating nuclear power generating sets evaporator feedwater - Google Patents
A kind of system for heating nuclear power generating sets evaporator feedwater Download PDFInfo
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- CN206572497U CN206572497U CN201720180586.3U CN201720180586U CN206572497U CN 206572497 U CN206572497 U CN 206572497U CN 201720180586 U CN201720180586 U CN 201720180586U CN 206572497 U CN206572497 U CN 206572497U
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- 238000010438 heat treatment Methods 0.000 title claims abstract description 20
- 230000001105 regulatory effect Effects 0.000 claims abstract description 20
- 238000000605 extraction Methods 0.000 claims abstract description 18
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 28
- 239000008236 heating water Substances 0.000 claims description 2
- 230000007423 decrease Effects 0.000 abstract 1
- 238000001704 evaporation Methods 0.000 abstract 1
- 230000008020 evaporation Effects 0.000 abstract 1
- 230000001276 controlling effect Effects 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000009977 dual effect Effects 0.000 description 1
- 230000009191 jumping Effects 0.000 description 1
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Abstract
A kind of system for heating nuclear power generating sets evaporator feedwater of the utility model, the system includes high pressure cylinder, low pressure (LP) cylinder, the first to the 8th valve group, bypass valve, evaporator, high-pressure heater, condenser, feed pump, oxygen-eliminating device, low-pressure heater, condensate pump.During operation, comprise the following steps：1) it is connected to from connecting pipe on the bypass duct before turbine by-pass regulating valve by valve group on the extraction line after high-pressure heater extraction line non-return flap；2) it is connected to from connecting pipe on the bypass duct before turbine by-pass regulating valve by valve group on the extraction line after oxygen-eliminating device extraction line non-return flap；3) it is connected to from connecting pipe on the bypass duct before turbine by-pass regulating valve by valve group on the extraction line after low-pressure heater extraction line non-return flap；4) during unit starting, shut down the not big good fortune of shutdown state, steam turbine load and decline operating mode; reject steam is introduced into high-pressure heater, oxygen-eliminating device, the feedwater of low-pressure heater heating evaporation device; reduce the fluctuation of evaporator inlet feed temperature, the safety of protection evaporator operation.
Description
The technical field is as follows:
the utility model belongs to the technical field of the nuclear power, concretely relates to system of heating nuclear power unit evaporimeter feedwater.
Background art:
high temperature gas cooled reactor nuclear power plants are currently configured in a dual reactor-single machine configuration. The feed water at the inlet of the evaporator is heated by the low-pressure heater, the deaerator and the high-pressure heater, so that the requirement of the water temperature at the inlet of the evaporator is met, and the normal steam sources of the low-pressure heater, the deaerator and the high-pressure heater are the extraction steam of the steam turbine.
The current system mainly has the following defects:
1) before the steam turbine is not loaded, steam extraction cannot be obtained, water supply of an evaporator can only supply steam to a deaerator for heating by starting a boiler, the boiler needs to be started for a long time, and the steam turbine is high in cost, poor in heating effect and unstable;
2) in the initial starting stage of the unit, a large amount of steam is discharged to the condenser through the bypass, and the steam discharged into the condenser cannot be utilized, so that the energy is wasted;
3) the steam is discharged into the condenser, so that the temperature of the condensed water is increased, and the efficiency of the steam turbine is reduced;
4) the operation of fine treatment can be influenced by overhigh temperature of the condensed water;
5) after steam enters the condenser and becomes condensed water, the condensed water is pumped into the deaerator by using the condensed water pump, so that the power consumption of the condensed water pump is increased;
6) when the steam turbine is shut down and does not stop, the steam extraction is completely lost after the steam turbine is shut down, the steam sources of the high-pressure heater, the low-pressure heater and the deaerator are completely lost, the water supply temperature at the inlet of the evaporator is sharply reduced, and the safety of the evaporator is influenced;
7) when the single-reactor stop working condition is carried out, the load of the steam turbine is reduced by 50%, the steam extraction pressure and the flow are reduced, the temperature of the inlet of the operating reactor is suddenly reduced, and the safety of the evaporator is influenced.
The utility model has the following contents:
an object of the utility model is to provide a system of heating nuclear power unit evaporimeter feedwater to the not enough of present nuclear power unit system.
In order to achieve the above purpose, the utility model adopts the following technical scheme to realize:
a system for heating water supply of an evaporator of a nuclear power unit comprises a high-pressure cylinder, a first valve group, a second valve group, a third valve group, a fourth valve group, a fifth valve group, a bypass regulating valve, a sixth valve group, a seventh valve group, an eighth valve group, a high-pressure heater, a condenser, a deaerator and a low-pressure heater; wherein,
the outlet of the first valve group is divided into two parts, the first part is connected with the inlet of the high-pressure cylinder, the second part is connected with the inlet of the bypass regulating valve, and the second part is called a bypass pipeline; the bypass pipeline is provided with three holes which are respectively connected with inlets of the second valve group, the seventh valve group and the eighth valve group through pipelines; the outlet pipelines of the second valve group and the third valve group are converged and then connected to a second inlet of the high-pressure heater through a sixth valve group; the outlet pipelines of the fourth valve group and the seventh valve group are converged and then connected to a second inlet of the deaerator; and the outlet pipelines of the fifth valve group and the eighth valve group are merged and then connected to a second inlet of the low-pressure heater.
The utility model has the further improvement that the device comprises a low pressure cylinder, an evaporator, a water feeding pump and a condensate pump; wherein,
the outlet of the deaerator is connected with the inlet of the feed pump; the outlet of the feed water pump is connected with the first inlet of the high-pressure heater; the outlet of the high-pressure heater is connected with the inlet of the evaporator; the outlet of the evaporator is connected with the inlet of the first valve group; the first outlet of the high-pressure cylinder is connected with the inlet of the third valve group, the second outlet of the high-pressure cylinder is connected with the inlet of the fourth valve group, and the third outlet of the high-pressure cylinder is connected with the inlet of the low-pressure cylinder; a first outlet of the low-pressure cylinder is connected with an inlet of the fifth valve group, and a second outlet of the low-pressure cylinder is connected with a first inlet of the condenser; the outlet of the bypass regulating valve is connected with the second inlet of the condenser; the outlet of the condenser is connected with the inlet of the condensate pump, and the outlet of the condensate pump is connected with the first inlet of the low-pressure heater; the outlet of the low-pressure heater is connected with the first inlet of the deaerator.
The utility model discloses further improvement lies in, and first valve group is by the door and the governing valve of evaporimeter export.
The utility model discloses further improvement lies in that second valve group, seventh valve group, eighth valve group are stop gate, regulating valve and check valve.
The utility model discloses further improvement lies in that third valve group, fourth valve group and fifth valve group are steam extraction stop gate and check valve.
The utility model discloses further improvement lies in, and sixth valve group is the stop gate.
Compared with the prior art, the utility model has the advantages of as follows:
the utility model relates to a system for heating nuclear power unit evaporimeter feedwater compares with the system that uses usually at present and has following several obvious advantages in the aspect:
1) the heat of partial bypass steam is directly recovered, and the energy-saving effect is achieved;
2) the temperature of the condensed water in the starting stage is reduced, and the efficiency of the steam turbine is improved;
3) the temperature of the condensed water in the starting stage is reduced, which is beneficial to the safe operation of the fine processing system;
4) the output of the condensate pump is reduced, and the energy-saving effect is achieved;
5) at the initial stage of starting, the temperature of feedwater is mainly heated by a deaerator, the heating steam source of the deaerator is used for starting a boiler, and the steam quantity for starting the boiler is limited, so that the feedwater temperature is generally difficult to improve;
7) after the steam turbine trips and the steam extraction of the steam turbine is lost, and the bypass is put into operation, the low-pressure heater, the deaerator and the high-pressure heater steam source are switched to bypass steam, so that the inlet temperature of the evaporator cannot fluctuate violently, and the operation safety of the unit is improved.
8) Under the working conditions that the load of the steam turbine is greatly reduced due to single-pile tripping and the like, after the bypass is put into operation, the steam sources of the low-pressure heater, the deaerator and the high-pressure heater are switched to bypass steam, the inlet temperature of the evaporator cannot fluctuate violently, and the operation safety of the unit is improved.
Description of the drawings:
FIG. 1 is a block diagram of a system for heating feedwater for a nuclear power plant evaporator.
In the figure: 1-high pressure cylinder, 2-low pressure cylinder, 3-first valve group, 4-second valve group, 5-third valve group, 6-fourth valve group, 7-fifth valve group, 8-bypass regulating valve, 9-evaporator, 10-sixth valve group, 11-seventh valve group, 12-eighth valve group, 13-high pressure heater, 14-condenser, 15-water supply pump, 16-deaerator, 17-low pressure heater and 18-condensate pump.
The specific implementation mode is as follows:
the present invention will be described in further detail with reference to the accompanying drawings.
As shown in fig. 1, the utility model provides a system for heating nuclear power generating set evaporimeter feedwater, including high-pressure cylinder 1, low-pressure cylinder 2, first valve group 3, second valve group 4, third valve group 5, fourth valve group 6, fifth valve group 7, bypass control valve 8, evaporimeter 9, sixth valve group 10, seventh valve group 11, eighth valve group 12, high pressure heater 13, condenser 14, feed pump 15, oxygen-eliminating device 16, low pressure heater 17 and condensate pump 18; wherein, the outlet of the deaerator 16 is connected with the inlet of the feed water pump 15; the outlet of the feed water pump 15 is connected with the first inlet of the high-pressure heater 13; the outlet of the high-pressure heater 13 is connected with the inlet of the evaporator 9; the outlet of the evaporator 9 is connected with the inlet of the first valve group 3; the outlet of the first valve group 3 is divided into two parts, the first part is connected with the inlet of the high pressure cylinder 1, the second part is connected with the inlet of the bypass regulating valve 8, and the second part is called a bypass pipeline; the bypass pipeline is provided with three holes and is respectively connected with the inlets of the second valve group 4, the seventh valve group 11 and the eighth valve group 12 through pipelines; the outlet pipelines of the second valve group 4 and the third valve group 5 are converged and then connected to a second inlet of the high-pressure heater 13 through a sixth valve group 10; the outlet pipelines of the fourth valve group 6 and the seventh valve group 11 are merged and then connected to a second inlet of the deaerator 16; the outlet pipelines of the fifth valve group 7 and the eighth valve group 12 are merged and then connected to a second inlet of the low-pressure heater 17; a first outlet of the high-pressure cylinder 1 is connected with an inlet of the third valve group 5, a second outlet of the high-pressure cylinder 1 is connected with an inlet of the fourth valve group 6, and a third outlet of the high-pressure cylinder 1 is connected with an inlet of the low-pressure cylinder 2; a first outlet of the low-pressure cylinder 2 is connected with an inlet of the fifth valve group 7, and a second outlet of the low-pressure cylinder 2 is connected with a first inlet of the condenser 14; the outlet of the bypass regulating valve 8 is connected with the second inlet of the condenser 14; the outlet of the condenser 14 is connected with the inlet of a condensate pump 18, and the outlet of the condensate pump 18 is connected with the first inlet of the low-pressure heater 17; the outlet of the low-pressure heater 17 is connected with the first inlet of the deaerator 16.
The first valve group 3 is a stop gate and an adjusting gate at the outlet of the evaporator 9.
The second valve group 4, the seventh valve group 11 and the eighth valve group 12 are all stop valves, regulating valves and check valves.
And the third valve group 5, the fourth valve group 6 and the fifth valve group 7 are all steam extraction stop valves and check valves.
The sixth valve group 10 is a stop valve.
For further understanding of the present invention, the following description is made to the operation process thereof:
1) after the reactor is started and before the steam turbine is flushed, steam generated by the evaporator 9 is discharged into the condenser through the bypass regulating valve 8;
2) opening a stop valve in the ninth valve group 12, controlling steam to enter the low-pressure heater 17 through a regulating valve of the ninth valve group 12, and putting the low-pressure heater 17 into the low-pressure heater 17 to heat the inlet feed water of the evaporator;
3) opening a stop valve in the eighth valve group 11, controlling steam to enter a deaerator 16 through a regulating valve of the eighth valve group 11, and putting the deaerator 16 to heat inlet feed water of the evaporator;
4) opening the stop valves in the third valve group 5 and the seventh valve group 10, controlling steam to enter the high-pressure heater 13 through the regulating valve of the third valve group 5, and putting the high-pressure heater 13 to heat the inlet feed water of the evaporator;
5) after the steam turbine is charged with load by impulse rotation, the bypass steam is reduced along with the increase of the load of the steam turbine, when the steam extraction amount of the steam turbine meets the requirement of water supply heating of the evaporator, the steam sources of the low-pressure heater 17, the deaerator 16 and the high-pressure heater 13 are switched to extract steam, and the water supply of the evaporator is heated by the extracted steam;
6) under the working condition that the turbine is not in a stack jumping state, the steam source of the steam turbine is cut off, after a bypass is put into operation, the steam sources of the low-pressure heater 17, the deaerator 16 and the high-pressure heater 13 are switched to bypass steam, the bypass steam is used for heating the feed water of the evaporator, the steam temperature at the inlet of the evaporator is prevented from being greatly reduced, and the safety of the evaporator is protected;
7) when the load of the steam turbine reduces the insufficient extraction pressure, the steam sources of the low-pressure heater 17, the deaerator 16 and the high-pressure heater 13 are switched into bypass steam, the bypass steam is used for heating the feed water of the evaporator, the steam temperature at the inlet of the evaporator is prevented from greatly fluctuating, and the safety of the evaporator is protected;
8) in a nuclear power unit with double reactors and one machine, one reactor jumps and the other reactor normally operates, the load of a steam turbine is reduced to be below 50% of the load, the steam extraction pressure of the steam turbine is reduced, and the steam extraction quantity is reduced, so that the inlet temperature of an operating evaporator is reduced, and the safety of the evaporator is influenced. At this time, a bypass can be put into the evaporator, and the bypass steam is used for supplying steam to the low-pressure heater 17, the deaerator 16 and the high-pressure heater 13, so that the water supply temperature at the inlet of the evaporator is ensured.
Claims (6)
1. A system for heating water supply of an evaporator of a nuclear power unit is characterized by comprising a high-pressure cylinder (1), a first valve group (3), a second valve group (4), a third valve group (5), a fourth valve group (6), a fifth valve group (7), a bypass regulating valve (8), a sixth valve group (10), a seventh valve group (11), an eighth valve group (12), a high-pressure heater (13), a condenser (14), a deaerator (16) and a low-pressure heater (17); wherein,
the outlet of the first valve group (3) is divided into two parts, the first part is connected with the inlet of the high-pressure cylinder (1), the second part is connected with the inlet of the bypass regulating valve (8), and the second part is called as a bypass pipeline; the bypass pipeline is provided with three holes and is respectively connected with inlets of the second valve group (4), the seventh valve group (11) and the eighth valve group (12) through pipelines; outlet pipelines of the second valve group (4) and the third valve group (5) are converged and then connected to a second inlet of the high-pressure heater (13) through a sixth valve group (10); the outlet pipelines of the fourth valve group (6) and the seventh valve group (11) are merged and then connected to a second inlet of the deaerator (16); the outlet pipelines of the fifth valve group (7) and the eighth valve group (12) are merged and then connected to a second inlet of the low-pressure heater (17).
2. The system for heating nuclear power plant evaporator feedwater according to claim 1, comprising a low pressure cylinder (2), an evaporator (9), a feedwater pump (15) and a condensate pump (18); wherein,
the outlet of the deaerator (16) is connected with the inlet of the water feeding pump (15); the outlet of the water feeding pump (15) is connected with the first inlet of the high-pressure heater (13); the outlet of the high-pressure heater (13) is connected with the inlet of the evaporator (9); the outlet of the evaporator (9) is connected with the inlet of the first valve group (3); a first outlet of the high-pressure cylinder (1) is connected with an inlet of the third valve group (5), a second outlet of the high-pressure cylinder (1) is connected with an inlet of the fourth valve group (6), and a third outlet of the high-pressure cylinder (1) is connected with an inlet of the low-pressure cylinder (2); a first outlet of the low-pressure cylinder (2) is connected with an inlet of the fifth valve group (7), and a second outlet of the low-pressure cylinder (2) is connected with a first inlet of the condenser (14); the outlet of the bypass regulating valve (8) is connected with the second inlet of the condenser (14); the outlet of the condenser (14) is connected with the inlet of a condensate pump (18), and the outlet of the condensate pump (18) is connected with the first inlet of the low-pressure heater (17); the outlet of the low-pressure heater (17) is connected with the first inlet of the deaerator (16).
3. The system for heating nuclear power plant evaporator feedwater according to claim 1, wherein the first valve set (3) is a stop gate and a regulating gate of the evaporator (9) outlet.
4. The system for heating nuclear power generating unit evaporator feedwater according to claim 1, wherein the second valve group (4), the seventh valve group (11), and the eighth valve group (12) are all stop valves, regulating valves, and check valves.
5. The system for heating feedwater for a nuclear power unit evaporator of claim 1, wherein the third valve set (5), the fourth valve set (6), and the fifth valve set (7) are each an extraction stop valve and a check valve.
6. The system for heating nuclear power unit evaporator feedwater of claim 1 wherein the sixth valve set (10) is a shut-off valve.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201720180586.3U CN206572497U (en) | 2017-02-27 | 2017-02-27 | A kind of system for heating nuclear power generating sets evaporator feedwater |
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| CN201720180586.3U CN206572497U (en) | 2017-02-27 | 2017-02-27 | A kind of system for heating nuclear power generating sets evaporator feedwater |
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| CN206572497U true CN206572497U (en) | 2017-10-20 |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106678770A (en) * | 2017-02-27 | 2017-05-17 | 西安热工研究院有限公司 | System and method for heating feed water of evaporator of nuclear power unit |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106678770A (en) * | 2017-02-27 | 2017-05-17 | 西安热工研究院有限公司 | System and method for heating feed water of evaporator of nuclear power unit |
| CN106678770B (en) * | 2017-02-27 | 2023-05-30 | 西安热工研究院有限公司 | System and method for heating water supply of evaporator of nuclear power unit |
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