CN207750972U - A kind of system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery - Google Patents
A kind of system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery Download PDFInfo
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- CN207750972U CN207750972U CN201820036907.7U CN201820036907U CN207750972U CN 207750972 U CN207750972 U CN 207750972U CN 201820036907 U CN201820036907 U CN 201820036907U CN 207750972 U CN207750972 U CN 207750972U
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Abstract
A kind of system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery of the utility model, which includes steam turbine, steam-water separator, Pan Lu, the first valve group, the second valve group, third valve group, the 4th valve group, evaporator, condenser, unit rhone, high-pressure feed water system, oxygen-eliminating device and low pressure feed water system.When work, include the following steps：1) evaporator outlet working medium enters steam-water separator, and steam-water separation is carried out in steam-water separator, and water is discharged to main vapour system in separator lower part, vapour from steam-water separator top；2) before the water quality in steam-water separator is not up to recycling standard, unit rhone is drained into；3) water quality in steam-water separator reaches the pressure that the pressure after recycling standard and in steam-water separator is higher than oxygen-eliminating device, hydrophobic to drain into oxygen-eliminating device；4) it is hydrophobic to drain into condenser before the water quality in steam-water separator reaches the pressure after recycling standard and in steam-water separator not higher than the pressure of oxygen-eliminating device.
Description
Technical field
The utility model belongs to technical field of nuclear power, and in particular to a kind of high temperature gas cooled reactor nuclear power generating sets steam-water separator is thin
The system of water recycling.
Background technology
It is hydrophobic in the current steam-water separator of HTGR Nuclear Power Plant, in water quality qualification heel row toward condenser.
System is primarily present following deficiency at present：
1) hydrophobic in steam-water separator, after unit starting, there is certain temperature and pressure, after being discharged into condenser,
Heat possessed by these water can not recycle, and all waste.
2) water with heat is discharged into condenser, improves the temperature of condensed water, reduces the efficiency of steam turbine；
3) the excessively high operation that can influence precision processing of the temperature of condensed water；
4) be discharged into the water of condenser will also squeeze into oxygen-eliminating device using condensate pump, increase the wasted work of condensate pump；
5) when shutting down not shutdown operating condition, after halt turbines, steam extraction all loses, and auxiliary vapour header loses vapour
Source, evaporator inlet temperature are difficult to improve, and have influenced the safe operation of evaporator.
Utility model content
The purpose of this utility model is that for the deficiency of current machine set system, a kind of high temperature gas cooled reactor nuclear power machine is provided
The system of group steam-water separator drain recovery.
In order to achieve the above objectives, what the utility model adopts the following technical solution to realize：
A kind of system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery, including steam turbine, steam-water separator,
It bypass, the first valve group, the second valve group, third valve group, the 4th valve group, evaporator, condenser, unit rhone and removes
Oxygen device；Wherein,
The outlet of evaporator is connected on the entrance of steam-water separator, and the first outlet of steam-water separator meets entering for the first valve group
Mouthful, the second outlet of steam-water separator connects the entrance of steam turbine, the trepanning company on the pipeline among steam-water separator and steam turbine
Take over road to the entrance bypassed, the outlet of steam turbine connects the first entrance of condenser, and the outlet of bypass connects the second of condenser and enters
Mouthful, the outlet of the first valve group is divided into three strands, and first strand of entrance for being connected on the second valve group, second strand is connected on third valve group
Entrance, third stock are connected on the entrance of the 4th valve group, and the outlet of the second valve group is connected on the third entrance of condenser, third valve
The outlet of group is connected on the entrance of unit rhone, and the outlet of the 4th valve group is connected on the second entrance of oxygen-eliminating device.
The utility model, which further improves, to be, further includes low pressure feed water system, the outlet of condenser be connected on low pressure to
The entrance of water system, the outlet of low pressure feed water system are connected on the first entrance of oxygen-eliminating device.
The utility model, which further improves, to be, further includes high-pressure feed water system, the outlet of oxygen-eliminating device be connected on high pressure to
The entrance of water system, the outlet of high-pressure feed water system are connected on the entrance of evaporator.
The utility model, which further improves, to be, the first valve group and the second valve group are cut-off gate and adjusting door group
At valve group.
The utility model, which further improves, to be, third valve group and the 4th valve group are cut-off gate and adjusting door group
At valve group.
Compared with the existing technology, the utility model has the following advantages：
A kind of system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery provided by the utility model, have with
Lower several respects clear advantage：
1) it is recycled the separator with heat is hydrophobic, there is energy-saving effect；
2) oxygen-eliminating device outlet feed temperature is improved, it is advantageous to the safe operation of evaporator；
3) reduce unit using the dosage of external steam heating deaerator feedwater, there is energy-efficient effect；
4) reduce dependence of the unit to external steam, be conducive to the safe and stable operation of nuclear power generating sets；
5) temperature for reducing startup stage condensed water improves the efficiency of steam turbine；
6) temperature for reducing startup stage condensed water is advantageous to the safe operation of precision processing system；
7) output for reducing solidifying pump, has energy-saving effect.
Description of the drawings
Fig. 1 is a kind of structural frames of the system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery of the utility model
Figure.
In figure：1- steam turbines, 2- steam-water separators, 3- bypasses, the first valve groups of 4-, the second valve groups of 5-, 6- third valves
Door group, the 4th valve groups of 7-, 8- evaporators, 9- condensers, 10- unit rhones, 11- high-pressure feed water systems, 12- oxygen-eliminating devices,
13- low pressure feed water systems.
Specific implementation mode
The utility model is further described in detail below in conjunction with attached drawing.
As shown in Figure 1, a kind of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery provided by the utility model
System, including steam turbine 1, steam-water separator 2, the 3, first valve group 4 of bypass, the second valve group 5, third valve group 6, the 4th valve
Door group 7, evaporator 8, condenser 9, unit rhone 10, oxygen-eliminating device 12；Wherein, the outlet of evaporator 8 is connected on steam-water separator 2
Entrance, the first outlet of steam-water separator 2 connects the entrance of the first valve group 4, and the second outlet of steam-water separator 2 connects steam turbine
1 entrance, the entrance of trepanning connecting pipe extremely bypass 3 on the pipeline among steam-water separator 2 and steam turbine 1, steam turbine 1
Outlet connects the first entrance of condenser 9, and the outlet for bypassing 3 connects the second entrance of condenser 9, and the outlet of the first valve group 4 is divided into
Three strands, first strand of entrance for being connected on the second valve group 5, second strand of entrance for being connected on third valve group 6, third stock is connected on the 4th valve
The entrance of door group 7, the outlet of the second valve group 5 are connected on the third entrance of condenser 9, and the outlet of third valve group 6 is connected on unit
The entrance of rhone 10, the outlet of the 4th valve group 7 are connected on the second entrance of oxygen-eliminating device 12.
In addition, the utility model further includes low pressure feed water system 13 and high-pressure feed water system 11；Wherein, condenser 9 goes out
Mouth is connected on the entrance of low pressure feed water system 13, and the outlet of low pressure feed water system 13 is connected on the first entrance of oxygen-eliminating device 12, oxygen-eliminating device
12 outlet is connected on the entrance of high-pressure feed water system 11, and the outlet of high-pressure feed water system 11 is connected on the entrance of evaporator 8.Wherein,
First valve group 4, the second valve group 5, third valve group 6, the 4th valve group 7 are cut-off gate and adjust the valve of door composition
Group.
When work, the utility model includes the following steps：
1) the outlet working medium of evaporator 8 enters steam-water separator 2, and steam-water separation is carried out in steam-water separator 2, is isolated
The water come is known as that separator is hydrophobic, and water is discharged from the first outlet of steam-water separator 2, second outlet of the vapour from steam-water separator 2
Discharge；
2) before the drain water quality in steam-water separator 2 is not up to recycling standard, hydrophobic in steam-water separator 2 passes through vapour
The first outlet of separator 2, the first valve group 4, third valve group 6 drain into unit rhone 10；
3) drain water quality in steam-water separator 2 reaches the pressure after recycling standard and in steam-water separator 2 higher than removing
The pressure of oxygen device 12, the hydrophobic first outlet, the first valve group 4, the 4th valve by steam-water separator 2 in steam-water separator 2
Door group 7 drains into oxygen-eliminating device 12, then enters evaporator 8 by high-pressure feed water system 11；
4) water quality in steam-water separator 2 reaches the pressure after recycling standard and in steam-water separator 2 and is not higher than deoxygenation
Before the pressure of device 12, first outlet, the first valve group 4 and the second valve that the water in steam-water separator 2 passes through steam-water separator 2
Group 5 drains into condenser 9；
5) steam being discharged by the second outlet of steam-water separator 2 enters condenser by steam turbine 1 or bypass 3
9；
6) water in condenser enters evaporator by low pressure feed water system 13, oxygen-eliminating device 12 and high-pressure feed water system 11
8。
Claims (5)
1. a kind of system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery, which is characterized in that including steam turbine
(1), steam-water separator (2), bypass (3), the first valve group (4), the second valve group (5), third valve group (6), the 4th valve
Group (7), evaporator (8), condenser (9), unit rhone (10) and oxygen-eliminating device (12)；Wherein,
The outlet of evaporator (8) is connected on the entrance of steam-water separator (2), and the first outlet of steam-water separator (2) connects the first valve
The second outlet of the entrance of group (4), steam-water separator (2) connects the entrance of steam turbine (1), in steam-water separator (2) and steam turbine
(1) to the entrance for bypassing (3), the outlet of steam turbine (1) connects the first of condenser (9) and enters trepanning connecting pipe on intermediate pipeline
Mouthful, the outlet of bypass (3) connects the second entrance of condenser (9), and the outlet of the first valve group (4) is divided into three strands, and first strand is connected on
The entrance of second valve group (5), second strand of entrance for being connected on third valve group (6), third stock are connected on entering for the 4th valve group (7)
Mouthful, the outlet of the second valve group (5) is connected on the third entrance of condenser (9), and the outlet of third valve group (6) is connected on unit draining
The outlet of the entrance of slot (10), the 4th valve group (7) is connected on the second entrance of oxygen-eliminating device (12).
2. a kind of system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery according to claim 1, special
Sign is, further includes low pressure feed water system (13), and the outlet of condenser (9) is connected on the entrance of low pressure feed water system (13), low pressure
The outlet of water supply system (13) is connected on the first entrance of oxygen-eliminating device (12).
3. a kind of system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery according to claim 2, special
Sign is, further includes high-pressure feed water system (11), and the outlet of oxygen-eliminating device (12) is connected on the entrance of high-pressure feed water system (11), high pressure
The outlet of water supply system (11) is connected on the entrance of evaporator (8).
4. a kind of system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery according to claim 1, special
Sign is that the first valve group (4) and the second valve group (5) are cut-off gate and adjust the valve group of door composition.
5. a kind of system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery according to claim 1, special
Sign is that third valve group (6) and the 4th valve group (7) are cut-off gate and adjust the valve group of door composition.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201820036907.7U CN207750972U (en) | 2018-01-09 | 2018-01-09 | A kind of system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201820036907.7U CN207750972U (en) | 2018-01-09 | 2018-01-09 | A kind of system of high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery |
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| CN207750972U true CN207750972U (en) | 2018-08-21 |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108036301A (en) * | 2018-01-09 | 2018-05-15 | 西安热工研究院有限公司 | A kind of system and method for high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery |
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2018
- 2018-01-09 CN CN201820036907.7U patent/CN207750972U/en active Active
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108036301A (en) * | 2018-01-09 | 2018-05-15 | 西安热工研究院有限公司 | A kind of system and method for high temperature gas cooled reactor nuclear power generating sets steam-water separator drain recovery |
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