CN116857633A - Main water supply system of fast reactor - Google Patents
Main water supply system of fast reactor Download PDFInfo
- Publication number
- CN116857633A CN116857633A CN202310660507.9A CN202310660507A CN116857633A CN 116857633 A CN116857633 A CN 116857633A CN 202310660507 A CN202310660507 A CN 202310660507A CN 116857633 A CN116857633 A CN 116857633A
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- Prior art keywords
- water supply
- valve
- module
- regulating valve
- main water
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 190
- 230000001105 regulatory effect Effects 0.000 claims abstract description 97
- 238000002955 isolation Methods 0.000 claims abstract description 51
- 238000011144 upstream manufacturing Methods 0.000 claims description 22
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 abstract description 7
- 229910052708 sodium Inorganic materials 0.000 abstract description 7
- 239000011734 sodium Substances 0.000 abstract description 7
- 238000006243 chemical reaction Methods 0.000 abstract description 5
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000004200 deflagration Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000004020 luminiscence type Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22D—PREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
- F22D5/00—Controlling water feed or water level; Automatic water feeding or water-level regulators
- F22D5/26—Automatic feed-control systems
- F22D5/34—Applications of valves
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention relates to a fast reactor main water supply system. By adopting the fast reactor main water supply system provided by the invention, the water supply flow of each main water supply module to the steam generator can be ensured to be consistent by adjusting the module adjusting valve arranged on each main water supply module; meanwhile, different water supply flows can be provided through the regulating valve group according to the power state of the power plant, and the regulation precision of the main water supply flow is ensured. In addition, when the steam generator leaks, the fast reactor main water supply system provided by the invention can prevent water from continuously entering the steam generator by closing the downstream isolation valve and the fast isolation valve of the module regulating valve; and then the water stored in the steam generator can be discharged by opening the first water discharge valve after the accident and the second water discharge valve after the accident, so that the sodium water reaction result is slowed down, and the operation requirement of the fast reactor nuclear power plant is met.
Description
Technical Field
The invention belongs to the technical field of system design of high-temperature high-pressure piping of nuclear power plants, and particularly relates to a fast reactor main water supply system.
Background
The main water supply system has a very important meaning for the operation of the fast reactor nuclear power station, and the main function of the main water supply system is to supply high-pressure water heated by the high-pressure heater to the steam generator.
In the existing domestic fast reactor nuclear power station, a single reactor is provided with 16 steam generators with the same specification, and it is difficult to supply water with the same flow rate to each steam generator only by the arrangement of the existing system. In addition, after the heat transfer tube of the steam generator of the sodium-cooled fast neutron reactor nuclear power plant is damaged, the sodium is contacted with water or steam and has severe chemical reactions accompanied by the phenomena of temperature rise, deflagration, luminescence and the like, so that the operation of the fast reactor nuclear power plant is affected.
Disclosure of Invention
Aiming at the defects existing in the prior art, the invention aims to provide a fast reactor main water supply system, which maintains the same water supply flow rate of each module through system design, and can quickly isolate the steam generators and discharge water stored in the steam generators after sodium water leakage occurs in the steam generators, thereby ensuring that each steam generator is supplied with water with the same flow rate, simultaneously furthest reducing the influence of sodium water leakage of the steam generators on the operation of a fast reactor nuclear power station and ensuring the stability of long-term operation of the system.
In order to achieve the above purpose, the invention adopts the technical scheme that: a fast reactor main water supply system comprising:
a main water supply pipe;
the system comprises 16 main water supply modules, wherein each main water supply module comprises a module water supply pipeline, and an orifice plate flowmeter, a module regulating valve upstream isolating valve, a module regulating valve and a module regulating valve downstream isolating valve are sequentially connected in series on the module water supply pipeline along the water supply direction;
the two loops are connected in parallel with the outlet end of the main water supply pipe, each loop comprises a main water supply loop pipeline, and a venturi flowmeter and a regulating valve group are sequentially arranged on the main water supply loop pipeline along the water supply direction; each loop is connected with 8 main water supply modules, and the 8 main water supply modules are sequentially arranged at the downstream of the regulating valve group along the water supply direction.
Further, each loop further comprises a differential pressure measuring device, and two ends of the differential pressure measuring device are respectively connected with an upstream pipeline and a downstream pipeline of the regulating valve group.
Further, during the operation of the fast reactor, the front-back pressure difference of the regulating valve group is maintained between 1.0 and 1.1 MPa.
Further, the regulating valve group includes: the loop regulating valve group and the bypass regulating valve group are arranged on the main water supply loop pipeline in parallel;
the loop regulating valve group comprises an upstream electric isolating valve, a main water supply loop regulating valve and a downstream electric isolating valve of the loop regulating valve which are sequentially connected in series along the water supply direction;
the bypass regulating valve group comprises a bypass regulating valve upstream electric isolation valve, a main water supply bypass regulating valve and a bypass regulating valve downstream electric isolation valve which are sequentially connected in series along the main water supply direction.
Further, when the power plant is in a low power state below 28% rated power, the main feedwater loop regulator valve is closed and feedwater flow is regulated by the main feedwater bypass regulator valve.
Further, when the power plant is in a high power state above 28% rated power, the main feedwater bypass regulator valve maintains a fixed opening, and feedwater flow is regulated by the main feedwater loop regulator valve.
Further, each main water supply module is connected with the loop through a first end of the module water supply pipeline and is connected with a corresponding steam generator through a second end of the module water supply pipeline;
and on the module water supply pipeline, a rapid isolation valve, a module pressure measuring device and a module temperature measuring device are sequentially connected in series along the water supply direction at the downstream of the downstream isolation valve of the module regulating valve.
Further, each of the main water supply modules further includes a post-accident water drain pipe, a first end of the post-accident water drain pipe is connected to the module water supply pipe, and a first end of the post-accident water drain pipe is disposed downstream of the quick isolation valve.
Further, the post-accident water draining pipeline is serially provided with a post-accident first water draining valve and a post-accident second water draining valve.
And if the steam generator leaks, closing the downstream isolation valve and the rapid isolation valve of the module adjusting valve, and opening the first drainage valve after the accident and the second drainage valve after the accident.
The invention has the beneficial effects that: by adopting the fast reactor main water supply system provided by the invention, the water supply flow of each main water supply module to the steam generator can be ensured to be consistent by adjusting the module adjusting valve arranged on each main water supply module; meanwhile, different water supply flows can be provided through the regulating valve group according to the power state of the power plant, and the regulation precision of the main water supply flow is ensured. In addition, when the steam generator leaks, the fast reactor main water supply system provided by the invention can prevent water from continuously entering the steam generator by closing the downstream isolation valve and the fast isolation valve of the module regulating valve; and then the water stored in the steam generator can be discharged by opening the first water discharge valve after the accident and the second water discharge valve after the accident, so that the sodium water reaction result is slowed down, and the operation requirement of the fast reactor nuclear power plant is met.
Drawings
FIG. 1 is a schematic diagram of a primary water supply system for a fast reactor according to an embodiment of the present invention;
in the figure: the system comprises a 1-main water supply main pipe, a 2-main water supply loop pipeline, a 3-venturi flowmeter, a 4-main water supply loop regulating valve, a 5-main water supply bypass regulating valve, a 6-loop regulating valve upstream electric isolation valve, a 7-loop regulating valve downstream electric isolation valve, an 8-bypass regulating valve upstream electric isolation valve, a 9-bypass regulating valve downstream electric isolation valve, a 10-differential pressure measuring device, an 11-orifice plate flowmeter, a 12-module regulating valve upstream isolation valve, a 13-module regulating valve, a 14-module regulating valve downstream isolation valve, a 15-quick isolation valve, a 16-module water supply pipeline, a 17-module pressure measuring device, a 18-module temperature measuring device, a 19-post-accident drainage pipeline, a 20-post-accident first drainage valve and a 21-post-accident second drainage valve.
Detailed Description
In order that those skilled in the art will better understand the technical solutions of the present invention, the technical solutions of the embodiments of the present invention will be further clearly and completely described below with reference to the accompanying drawings in the embodiments of the present invention, and it is apparent that the described embodiments are only some embodiments of the present invention, but not all embodiments of the present invention.
As shown in fig. 1, the main water supply system of a fast reactor provided by the embodiment of the invention comprises: the main water supply pipe 1, two loops and 16 main water supply modules; the two loops are connected in parallel with the outlet end of the main water supply pipe 1, and each loop is connected with 8 main water supply modules.
The feed water enters the main feed water system of the fast reactor through the inlet end of the main feed water main pipe 1, then enters the main feed water module through the loop and finally enters the steam generator. In order to ensure the operation efficiency of the fast reactor nuclear power plant, the design pressure of the main water supply system of the fast reactor is 22.9MPa, and the design temperature is 230 ℃.
The two loops are a loop I and a loop II respectively, and the loop I and the loop II are arranged at the outlet end of the main water supply main pipe 1 in parallel. Each of the loop arrangements is identical and comprises a main feed water loop conduit 2, a venturi flow meter 3, a regulating valve set, and a differential pressure measuring device 10. The venturi flowmeter 3 and the regulating valve group are sequentially arranged on the main water supply loop pipeline 2 along the water supply direction; the two ends of the differential pressure measuring device 10 are respectively connected with an upstream pipeline and a downstream pipeline of the regulating valve group, and the differential pressure measuring device 10 monitors the operation condition of the regulating valve group by measuring the differential pressure of the front and the rear of the regulating valve group. During the operation of the fast reactor, the front-back pressure difference of the regulating valve group is maintained between 1.0 and 1.1 MPa.
The regulating valve group includes: the loop regulating valve group and the bypass regulating valve group are arranged on the main water supply loop pipeline 2 in parallel. The loop regulating valve group comprises a loop regulating valve upstream electric isolation valve 6, a main water supply loop regulating valve 4 and a loop regulating valve downstream electric isolation valve 7 which are sequentially connected in series along the water supply direction; the bypass regulating valve group comprises a bypass regulating valve upstream electric isolation valve 8, a main water supply bypass regulating valve 5 and a bypass regulating valve downstream electric isolation valve 9 which are sequentially connected in series along the main water supply direction. When the power plant is in a low power state (below 28% rated power), the required water supply flow is smaller, and in order to ensure the main water supply flow regulation precision, the main water supply loop regulating valve 4 is closed, and only the main water supply bypass regulating valve 5 is adopted to regulate the water supply flow; when the power plant is in a high power state (more than 28% of rated power), the main water supply bypass regulating valve 5 maintains a fixed opening, and water supply flow is regulated through the main water supply loop regulating valve 4, so that the accuracy of regulating the main water supply flow is ensured. The loop regulating valve upstream electric isolation valve 6 and the loop regulating valve downstream electric isolation valve 7 are used for overhauling the main water supply loop regulating valve 4, and when overhauling, the loop regulating valve upstream electric isolation valve 6 and the loop regulating valve downstream electric isolation valve 7 are closed, so that the main water supply loop regulating valve 4 can be overhauled or replaced. Similarly, the bypass regulating valve upstream electric isolation valve 8 and the bypass regulating valve downstream electric isolation valve 9 are used for overhauling the main water supply bypass regulating valve 5, and the bypass regulating valve upstream electric isolation valve 8 and the bypass regulating valve downstream electric isolation valve 9 are closed during overhauling, so that the main water supply bypass regulating valve 5 can be overhauled or replaced.
The 16 main water supply modules are evenly distributed on two loops, namely, each loop is connected with 8 main water supply modules. And 8 main water supply modules are sequentially arranged at the downstream of the regulating valve group along the water supply direction on each loop. Each main water supply module comprises an orifice plate flowmeter 11, a module regulating valve upstream isolating valve 12, a module regulating valve 13, a module regulating valve downstream isolating valve 14, a quick isolating valve 15, a module water supply pipeline 16, a module pressure measuring device 17, a module temperature measuring device 18, a post-accident water discharge pipeline 19, a post-accident first water discharge valve 20 and a post-accident second water discharge valve 21, wherein the orifice plate flowmeter 11, the module regulating valve upstream isolating valve 12, the module regulating valve 13, the module regulating valve downstream isolating valve 14, the quick isolating valve 15, the module pressure measuring device 17 and the module temperature measuring device 18 are sequentially connected on the module water supply pipeline 16 in series along the water supply direction. Each main water feed module is connected to one of said loops through a first end of the module water feed pipe 16 and to a corresponding steam generator through a second end of the module water feed pipe 16. The first end of the post-accident drainage pipeline 19 is connected with the module water supply pipeline 16, and the first end of the post-accident drainage pipeline 19 is arranged at the downstream of the quick isolation valve 15 (namely between the quick isolation valve 15 and the module pressure measuring device 17); the second end of the drainage pipeline 19 is connected with a water delivery and drainage pipeline after an accident. The post-accident first drain valve 20 and the post-accident second drain valve 21 are arranged in series on the post-accident drain pipe 19. The module regulating valve 13 is used for ensuring the flow consistency of 16 main water supply modules, and the orifice plate flowmeter 11 is used for measuring the flow value of each main water supply module. The upstream isolation valve 12 and the downstream isolation valve 14 of the module adjusting valve are used for overhauling the module adjusting valve 13, and the upstream isolation valve 12 and the downstream isolation valve 14 of the module adjusting valve are closed during overhauling, so that the module adjusting valve 13 can be overhauled or replaced. The orifice plate flowmeter 11, the module pressure measuring device 17 and the module temperature measuring device 18 are used for monitoring the operation condition of each main water supply module, and if the flow, the temperature and the pressure of one main water supply module deviate from the operation preset values or are inconsistent with the other main water supply modules, the main water supply modules can be isolated and overhauled.
When the steam generator leaks, the downstream isolation valve 14 and the rapid isolation valve 15 of the module adjusting valve are closed to isolate, so that the feed water is prevented from continuously entering the steam generator; the closing time of the downstream isolation valve 14 of the module adjusting valve is less than or equal to 15s, and the closing time of the rapid isolation valve 15 is less than or equal to 3s, so that the feed water can be rapidly prevented from continuously entering the steam generator. After the isolation is completed, the first water discharge valve 20 after the accident and the second water discharge valve 21 after the accident are opened, and the water stored in the steam generator is discharged, so that the sodium water reaction is slowed down. Therefore, the post-accident drain pipe 19 needs to be arranged downstream of the quick isolation valve 15, so that the water stored in the steam generator can still be discharged after the water supply is isolated.
According to the fast reactor main water supply pipeline system provided by the embodiment of the invention, the water supply flow of each main water supply module to the steam generator can be ensured to be consistent through the module regulating valve 13 on each main water supply module; different water supply flows can be provided through the regulating valve group according to the power state of the power plant, and the regulation precision of the main water supply flow is ensured. In addition, when the steam generator leaks, the downstream isolation valve 14 and the rapid isolation valve 15 of the module adjusting valve are closed, so that water can be prevented from continuously entering the steam generator, and water stored in the steam generator can be discharged by opening the first drain valve 20 after an accident and the second drain valve 21 after the accident, and the result of sodium water reaction is slowed down, so that the operation requirement of the fast reactor nuclear power plant is met.
The method of the present invention is not limited to the specific embodiments described above, which are merely illustrative of the present invention, and the present invention may be embodied in other specific forms or with other specific forms without departing from the spirit or essential characteristics of the present invention. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims are intended to be encompassed within the scope of the invention.
Claims (10)
1. A main water supply system for a fast reactor, comprising:
a main water supply pipe;
the system comprises 16 main water supply modules, wherein each main water supply module comprises a module water supply pipeline, and an orifice plate flowmeter, a module regulating valve upstream isolating valve, a module regulating valve and a module regulating valve downstream isolating valve are sequentially connected in series on the module water supply pipeline along the water supply direction;
the two loops are connected in parallel with the outlet end of the main water supply pipe, each loop comprises a main water supply loop pipeline, and a venturi flowmeter and a regulating valve group are sequentially arranged on the main water supply loop pipeline along the water supply direction; each loop is connected with 8 main water supply modules, and the 8 main water supply modules are sequentially arranged at the downstream of the regulating valve group along the water supply direction.
2. A main water supply system for a fast reactor according to claim 1, wherein each loop further comprises a differential pressure measuring device, and both ends of the differential pressure measuring device are respectively connected with an upstream pipeline and a downstream pipeline of the regulating valve group.
3. A main water supply system for a fast reactor according to claim 2, wherein the pressure difference between the front and rear of the regulating valve group is maintained between 1.0 MPa and 1.1MPa during operation of the fast reactor.
4. The primary water supply system of claim 1, wherein the regulator valve block comprises: the loop regulating valve group and the bypass regulating valve group are arranged on the main water supply loop pipeline in parallel;
the loop regulating valve group comprises an upstream electric isolating valve, a main water supply loop regulating valve and a downstream electric isolating valve of the loop regulating valve which are sequentially connected in series along the water supply direction;
the bypass regulating valve group comprises a bypass regulating valve upstream electric isolation valve, a main water supply bypass regulating valve and a bypass regulating valve downstream electric isolation valve which are sequentially connected in series along the main water supply direction.
5. The primary feed water system of claim 4, wherein the primary feed water loop regulator valve is closed and the feed water flow is regulated by the primary feed water bypass regulator valve when the power plant is in a low power state below 28% rated power.
6. The main fast reactor feedwater system of claim 4, wherein the main feedwater bypass regulator valve maintains a fixed opening when the power plant is in a high power state above 28% rated power, and feedwater flow is regulated by the main feedwater loop regulator valve.
7. A main water supply system for a fast reactor according to claim 1, wherein each of said main water supply modules is connected to said loop via a first end of said module water supply conduit and to a corresponding steam generator via a second end of said module water supply conduit;
and on the module water supply pipeline, a rapid isolation valve, a module pressure measuring device and a module temperature measuring device are sequentially connected in series along the water supply direction at the downstream of the downstream isolation valve of the module regulating valve.
8. The primary water supply system of claim 7, wherein each of the primary water supply modules further comprises a post-accident water drain, a first end of the post-accident water drain is connected to the module water supply, and a first end of the post-accident water drain is disposed downstream of the quick isolation valve.
9. The main water supply system of claim 8, wherein the post-accident water drain pipeline is provided with a post-accident first water drain valve and a post-accident second water drain valve in series.
10. The main water supply system of claim 9, wherein if steamed
When the steam generator leaks, the downstream isolation valve and the rapid isolation valve of the module adjusting valve are closed,
and opening the first drainage valve after the accident and the second drainage valve after the accident.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310660507.9A CN116857633A (en) | 2023-06-06 | 2023-06-06 | Main water supply system of fast reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310660507.9A CN116857633A (en) | 2023-06-06 | 2023-06-06 | Main water supply system of fast reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN116857633A true CN116857633A (en) | 2023-10-10 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202310660507.9A Pending CN116857633A (en) | 2023-06-06 | 2023-06-06 | Main water supply system of fast reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN116857633A (en) |
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2023
- 2023-06-06 CN CN202310660507.9A patent/CN116857633A/en active Pending
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