CN110579405A - Auxiliary water supply system of nuclear power station and heating method thereof - Google Patents
Auxiliary water supply system of nuclear power station and heating method thereof Download PDFInfo
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- CN110579405A CN110579405A CN201910806328.5A CN201910806328A CN110579405A CN 110579405 A CN110579405 A CN 110579405A CN 201910806328 A CN201910806328 A CN 201910806328A CN 110579405 A CN110579405 A CN 110579405A
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N3/00—Investigating strength properties of solid materials by application of mechanical stress
- G01N3/08—Investigating strength properties of solid materials by application of mechanical stress by applying steady tensile or compressive forces
- G01N3/10—Investigating strength properties of solid materials by application of mechanical stress by applying steady tensile or compressive forces generated by pneumatic or hydraulic pressure
- G01N3/12—Pressure testing
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N3/00—Investigating strength properties of solid materials by application of mechanical stress
- G01N3/08—Investigating strength properties of solid materials by application of mechanical stress by applying steady tensile or compressive forces
- G01N3/18—Performing tests at high or low temperatures
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Abstract
The invention relates to an auxiliary water supply system of a nuclear power station and a heating method thereof, wherein the auxiliary water supply system comprises: the water storage tank, a first circulation passage connecting the water inlet and the first water outlet of the water storage tank, and a second circulation passage connecting the water inlet and the second water outlet of the water storage tank; the first circulation path comprises a first isolation valve, a first water charging pump, a second isolation valve, an auxiliary water feeding deaerator, a second water charging pump, a three-way regulating valve and a third isolation valve which are sequentially connected in series, and a steam isolation valve and an auxiliary steam distribution system which are connected with the auxiliary water feeding deaerator; the second circulation path comprises a fourth isolating valve, a filter, an external heating device, a fifth isolating valve, a third water filling pump and a sixth isolating valve which are sequentially connected in series. The implementation of the invention can: the water temperature heating time is shortened, a sufficient window is obtained for related system maintenance, and the maintenance pressure is reduced.
Description
Technical Field
The invention relates to the technical field of heating of nuclear power stations, in particular to an auxiliary water supply system of a nuclear power station and a heating method thereof.
Background
According to RSE-M standard requirements, in the process of implementing a pressurized water reactor nuclear power station Steam Generator (SG) hydrostatic test, in order to avoid the risk of equipment damage caused by the increase of brittle transition temperature, the secondary side metal temperature of a test object SG is required to be higher than the test temperature by more than 43 ℃. The running program therefore stipulated that the hydrostatic test water in ASG001BA was heated to 50-55 ℃ before SG hydrostatic test. The water temperature of water filled into the SG hydraulic test system in the water filling stage is higher than the test temperature so as to reduce the metal cooling rate of the evaporator.
At present, before the SG hydraulic pressure test in China, the water quality of ASG001BA is heated, steam of an auxiliary steam distribution System (SVA) is subjected to heat exchange through an auxiliary water supply deaerator (ASG001DZ) to realize cyclic heating, and the heating can be realized only when systems such as SAR pneumatic head gas consumption, LLA equipment power consumption and the like are recovered in the overhaul stage.
The disadvantages of the prior art:
1) Heating can be carried out only after systems related to the cyclic heating of the systems are recovered;
2) Uncertainty exists in system maintenance work, and the function debugging of the SG hydraulic test device is influenced;
3) The original power station system circulation heating method cannot heat to the required water temperature.
disclosure of Invention
The invention aims to solve the technical problem of providing an auxiliary water supply system of a nuclear power station and a heating method thereof aiming at the defects of the prior art.
the technical scheme adopted by the invention for solving the technical problems is as follows: constructing a nuclear power plant secondary water supply system comprising: a water storage tank, a first circulation passage connecting a water inlet of the water storage tank with a first water outlet of the water storage tank, and a second circulation passage connecting a water inlet of the water storage tank with a second water outlet of the water storage tank;
The first circulation path comprises a first isolation valve, a first water charging pump, a second isolation valve, an auxiliary water supply deaerator, a second water charging pump, a three-way regulating valve and a third isolation valve which are sequentially connected in series, and a steam isolation valve and an auxiliary steam distribution system which are in loop connection with the auxiliary water supply deaerator, wherein the first isolation valve is connected with a first water outlet of the water storage tank, and the third isolation valve is connected with a water inlet of the water storage tank;
The second circulation path comprises a fourth isolation valve, a filter, an external heating device, a fifth isolation valve, a third water filling pump and a sixth isolation valve which are sequentially connected in series, the fourth isolation valve is connected with a water inlet of the water storage tank, and the sixth isolation valve is connected with a second water outlet of the water storage tank.
preferably, the water storage tank further comprises a three-way valve, a first end of the three-way valve is connected with the third isolation valve, a second end of the three-way valve is connected with the sixth isolation valve, and a third end of the three-way valve is connected with the water inlet of the water storage tank.
Preferably, the third isolation valve and the sixth isolation valve are detachably connected with the water inlet of the water storage tank.
Preferably, the third isolation valve is detachable from the water inlet of the water storage tank and can be connected with a blind flange.
Preferably, the external heating device comprises a heating water tank, and a liquid level transmitter, a temperature transmitter and an electric heating device which are arranged inside the heating water tank.
Preferably, the heating water tank has a level lower than or equal to that of the water storage tank.
Preferably, the second circulation path further comprises a flow meter connected to the water inlet of the water storage tank.
the invention also provides a heating method of the auxiliary water supply system of the nuclear power station, which is applied to the auxiliary water supply system of the nuclear power station and comprises the following steps:
And injecting water into the water storage tank through the first circulation passage, controlling the second circulation passage to be communicated with the water storage tank after the water storage tank is injected with water, and starting the external heating device to work.
the auxiliary water supply system for the nuclear power station and the heating method thereof have the following beneficial effects: the water temperature heating time is shortened, a sufficient window is obtained for related system maintenance, and the maintenance pressure is reduced.
drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic structural diagram of a first embodiment of an auxiliary feedwater system of a nuclear power plant according to the present invention;
fig. 2 is a schematic structural diagram of a nuclear power plant auxiliary water supply system according to a second embodiment of the invention.
Detailed Description
For a more clear understanding of the technical features, objects and effects of the present invention, embodiments of the present invention will now be described in detail with reference to the accompanying drawings.
as shown in fig. 1, in a first embodiment of an auxiliary feedwater system of a nuclear power plant according to the present invention, the auxiliary feedwater system includes: a water storage tank 30, a first circulation path 10 connecting a water inlet of the water storage tank 30 and a first water outlet of the water storage tank 30, and a second circulation path 20 connecting a water inlet of the water storage tank 30 and a second water outlet of the water storage tank 30; the first circulation path 10 comprises a first isolation valve 110, a first water charging pump 120, a second isolation valve 130, an auxiliary feed water deaerator 140, a second water charging pump 150, a three-way regulating valve 160 and a third isolation valve 170 which are sequentially connected in series, and a steam isolation valve 41 and an auxiliary steam distribution system 42 which are connected with the auxiliary feed water deaerator 140 in a loop way, wherein the first isolation valve 110 is connected with a first water outlet of the water storage tank 30, and the third isolation valve 170 is connected with a water inlet of the water storage tank 30; the second circulation path 20 includes a fourth isolation valve 210, a filter 220, an external heating device 230, a fifth isolation valve 240, a third water charging pump 250, and a sixth isolation valve 260 connected in series in this order, the fourth isolation valve 210 is connected to the water inlet of the water storage tank 30, and the sixth isolation valve 260 is connected to the second water outlet of the water storage tank 30. Specifically, the water storage tank 30 is a nuclear power auxiliary feed water storage tank ASG001BA, and its normal function is a backup system that supplies feed water to the SG secondary side when the main feed water supply is lost, and ASG001BA may provide heating water by the mutual cooperation of two circulation paths, wherein the first circulation path 10 is a first isolation valve 110, a first water-filled pump 120, a second isolation valve 130, an auxiliary feed water deaerator 140, a second water-filled pump 150, a three-way regulating valve 160, and a third isolation valve 170 that are connected in series in sequence. Where the auxiliary feedwater deaerator 140 is ASG001DZ, ASG001DZ is heated by the SVA system associated therewith, i.e., auxiliary steam distribution system 42, to provide heated water, and the flow rate of the heated steam therein is controlled by steam isolation valve 41 associated with auxiliary steam distribution system 42 to control the heating process for ASG001 DZ. The first isolation valve 110 is ASG163VD, the second isolation valve 130 is ASG153VD, the third isolation valve 170 is ASG115VD, the first water charging pump 120 is ASG006PO, the second water charging pump 150 is ASG005PO, and the three-way regulating valve 160 is ASG160VD, water in ASG001BA is firstly delivered to ASG001DZ by ASG006PO, then the water is heated by heat exchange between the heat transfer pipe of ASG001DZ and steam of the SVA system, and then hot water in ASG001DZ is delivered to ASG 36001 BA by pump pressure provided by ASG005 PO. The second circulation path 20 includes a fourth isolation valve 210, a filter 220, an external heating device 230, a fifth isolation valve 240, a third water charge pump 250, and a sixth isolation valve 260, which are connected in series in this order; the fourth isolating valve is ASG009VD, the filter 220 is ASG003FD, the fifth isolating valve can be a manual ball valve MD-52-PN16/DN100, and the third water charging pump can be CL 25801-122221. After the external heating device 230 heats the water, the water is pumped by the third water filling pump 250 to the ASG001BA, and meanwhile, the water in the ASG001BA circulates into the external heating device 230 for circular heating. Wherein ASG003FD is used to filter out impurities entering external heating device 230. It is understood that the first circulation path 10 and the second circulation path 20 are used in cooperation to supply heated water to the ASG001 BA.
optionally, the auxiliary water supply system for a nuclear power plant of the present invention further includes a three-way valve 181, a first end of the three-way valve 181 is connected to the third isolation valve 170, a second end of the three-way valve 181 is connected to the sixth isolation valve 260, and a third end of the three-way valve 181 is connected to a water inlet of the water storage tank 30. Specifically, the first circulation path 10 and the second circulation path 20 may be engaged with each other by the three-way valve 181, and for example, the first circulation path 10 and the second circulation path 20 may be respectively provided to be communicated with the tank 30 by controlling the third isolation valve 170 and the sixth isolation valve 260, thereby performing circulation of the heating water. It is also understood that the simultaneous conduction of the first circulation path 10 and the second circulation path 20 with the water storage tank 30 may be achieved by a tee joint
Optionally, the third isolation valve 170 and the sixth isolation valve 260 are detachably connected to the water inlet of the water storage tank 30. Specifically, the first circulation path 10 and the second circulation path 20 may be detachably connected to the water inlet of the water storage tank 30 through the third isolation valve 170 and the sixth isolation valve 260, respectively, and the first circulation path 10 and the second circulation path 20 may be respectively conducted to the water storage tank 30 to circulate the heated water by detaching the connection of the third isolation valve 170 and the sixth isolation valve 260 to the water inlet of the water storage tank 30, respectively. It will be understood herein that the first circulation path 10 and the second circulation path 20 are selectively communicated with the water inlet of the storage tank 30.
Alternatively, as shown in FIG. 2, the third isolation valve 170 may be removably connected to the inlet of the tank 30 and may be connected to a blind flange 182. Specifically, after the first circulation path 10 is disconnected from the water storage tank 30, one end of the first circulation path 10, i.e., the third isolation valve 170, may be disconnected from the water inlet of the water storage tank 30 and connected to a blind flange 182, so as to ensure the safety of the entire circulation path when the first circulation path 10 is not in use.
Optionally, the external heating device 230 includes a heating water tank 231, and a liquid level transmitter 232, a temperature transmitter 234 and an electric heating device 233 which are disposed inside the heating water tank 231. Specifically, the external heating device 230 may employ a heating water tank 231, and an electric heating device 233 is provided in the heating water tank 231 to heat water in the heating water tank, and a water level in the heating water tank is detected by a level transmitter 232 to perform a corresponding operation according to the water level. Meanwhile, the temperature of the water inside the heating water tank 233 can be detected by the temperature transmitter 234, so that the heating power of the electric heating device 233 is controlled according to the temperature of the water to heat the water in the heating water tank at a preset target temperature.
Alternatively, the heating water tank 231 may have a level lower than or equal to that of the water storage tank 30. Specifically, the heating water tank and the ASG001BA may be placed at the same level, and since the ASG001BA is higher and larger than the heating water tank, water is filled from the ASG001BA to the external heating water tank by gravity.
optionally, the second circulation path 20 further includes a flow meter connected to the water inlet of the water storage tank 30. Specifically, a flow meter is disposed on the pipeline of the combination device corresponding to the second circulation path 20, so that the pumping flow of the third water filling pump 250 can be matched by adjusting the opening degree of the water inlet valve of the heating water tank, i.e., the fourth isolation valve 210.
In addition, the invention relates to a heating method of an auxiliary water supply system of a nuclear power station, which is applied to the auxiliary water supply system of the nuclear power station and comprises the following steps:
the water storage tank 30 is filled with water through the first circulation path 10, and after the water storage tank 30 is filled with water, the second circulation path 20 is controlled to be communicated with the water storage tank 30, and the external heating device 230 starts to operate. Specifically, water may be supplied through the auxiliary water supply deaerator 140 in the first circulation path 10 connected to the water storage tank 30 to deaerate the circulating water during the circulation process, and when necessary, after the water is filled in the water storage tank 30, the water is conducted to the water storage tank 30 through the second circulation path 20, and the water storage tank 30 is cyclically heated by the external heating device 230.
In the embodiment: the system is not influenced by system recovery, and the water temperature condition can be achieved as early as possible to improve the test condition; the hydraulic test combination device can be debugged in advance, problems are found, and the debugging risk of hydraulic test equipment is reduced; the heating time can be reduced by using the power of the external heater so as to reduce the time cost; the standardized implementation level of the evaporator hydrostatic test project is improved; the water temperature may be heated to a higher temperature using an external heating system to increase the target water temperature.
It is to be understood that the foregoing examples, while indicating the preferred embodiments of the invention, are given by way of illustration and description, and are not to be construed as limiting the scope of the invention; it should be noted that, for those skilled in the art, the above technical features can be freely combined, and several changes and modifications can be made without departing from the concept of the present invention, which all belong to the protection scope of the present invention; therefore, all equivalent changes and modifications made within the scope of the claims of the present invention should be covered by the claims of the present invention.
Claims (8)
1. A nuclear power plant auxiliary water supply system, comprising: a water storage tank, a first circulation passage connecting a water inlet of the water storage tank with a first water outlet of the water storage tank, and a second circulation passage connecting a water inlet of the water storage tank with a second water outlet of the water storage tank;
The first circulation path comprises a first isolation valve, a first water charging pump, a second isolation valve, an auxiliary water supply deaerator, a second water charging pump, a three-way regulating valve and a third isolation valve which are sequentially connected in series, and a steam isolation valve and an auxiliary steam distribution system which are in loop connection with the auxiliary water supply deaerator, wherein the first isolation valve is connected with a first water outlet of the water storage tank, and the third isolation valve is connected with a water inlet of the water storage tank;
the second circulation path comprises a fourth isolation valve, a filter, an external heating device, a fifth isolation valve, a third water filling pump and a sixth isolation valve which are sequentially connected in series, the fourth isolation valve is connected with a water inlet of the water storage tank, and the sixth isolation valve is connected with a second water outlet of the water storage tank.
2. The nuclear power plant auxiliary water supply system according to claim 1, further comprising a three-way valve, wherein a first end of the three-way valve is connected to the third isolation valve, a second end of the three-way valve is connected to the sixth isolation valve, and a third end of the three-way valve is connected to a water inlet of the water storage tank.
3. The nuclear power plant auxiliary water supply system of claim 1, wherein the third isolation valve and the sixth isolation valve are removably connected to the water inlet of the water storage tank.
4. The nuclear power plant auxiliary water supply system according to claim 3, wherein the third isolation valve is detachably connected to a blind flange at the water inlet of the water storage tank.
5. The nuclear power plant auxiliary water supply system according to claim 1, wherein the external heating device includes a heating water tank, and a liquid level transmitter, a temperature transmitter, and an electric heating device provided inside the heating water tank.
6. The nuclear power plant feedwater system of claim 5, wherein the heating tank level is less than or equal to the storage tank level.
7. The nuclear power plant supplemental water supply system according to claim 1, wherein the second circulation path further includes a flow meter connected to a water inlet of the water storage tank.
8. A heating method of an auxiliary water supply system of a nuclear power station is characterized by comprising the following steps: the auxiliary water supply system of the nuclear power plant is applied to any one of claims 1 to 7, and comprises the following steps:
And injecting water into the water storage tank through the first circulation passage, controlling the second circulation passage to be communicated with the water storage tank after the water storage tank is injected with water, and starting the external heating device to work.
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| CN201910806328.5A CN110579405B (en) | 2019-08-29 | 2019-08-29 | Auxiliary water supply system of nuclear power station and heating method thereof |
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| CN201910806328.5A CN110579405B (en) | 2019-08-29 | 2019-08-29 | Auxiliary water supply system of nuclear power station and heating method thereof |
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| CN110579405B CN110579405B (en) | 2022-05-06 |
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Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN102192819A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | Quick heating process for pre-service hydrostatic test of secondary side of steam generator |
| CN102194535A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | Pre-service hydrostatic test integrated system on secondary side of steam generator |
| CN104848540A (en) * | 2015-06-10 | 2015-08-19 | 江苏天舒电器有限公司 | Primary heating type heat pump water heater and control method thereof |
| JP2017538134A (en) * | 2014-12-04 | 2017-12-21 | ジョイント・ストック・カンパニー サイエンティフィック リサーチ アンド デザイン インスティテュート フォー エナジー テクノロジーズ アトムプロエクト | A system for passive heat removal from a pressurized water reactor through a steam generator. |
| CN109799142A (en) * | 2018-12-20 | 2019-05-24 | 中广核核电运营有限公司 | Nuclear power station water pressure test loop heating system and circular heating method |
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2019
- 2019-08-29 CN CN201910806328.5A patent/CN110579405B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102192819A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | Quick heating process for pre-service hydrostatic test of secondary side of steam generator |
| CN102194535A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | Pre-service hydrostatic test integrated system on secondary side of steam generator |
| JP2017538134A (en) * | 2014-12-04 | 2017-12-21 | ジョイント・ストック・カンパニー サイエンティフィック リサーチ アンド デザイン インスティテュート フォー エナジー テクノロジーズ アトムプロエクト | A system for passive heat removal from a pressurized water reactor through a steam generator. |
| CN104848540A (en) * | 2015-06-10 | 2015-08-19 | 江苏天舒电器有限公司 | Primary heating type heat pump water heater and control method thereof |
| CN109799142A (en) * | 2018-12-20 | 2019-05-24 | 中广核核电运营有限公司 | Nuclear power station water pressure test loop heating system and circular heating method |
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