CN107131494A - Multi-module type HTGR Nuclear Power Plant water supply system - Google Patents
Multi-module type HTGR Nuclear Power Plant water supply system Download PDFInfo
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- CN107131494A CN107131494A CN201710283154.XA CN201710283154A CN107131494A CN 107131494 A CN107131494 A CN 107131494A CN 201710283154 A CN201710283154 A CN 201710283154A CN 107131494 A CN107131494 A CN 107131494A
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- pipeline
- main pipe
- pump group
- supply system
- power plant
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Classifications
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- 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
- F22D1/00—Feed-water heaters, i.e. economisers or like preheaters
- F22D1/50—Feed-water heaters, i.e. economisers or like preheaters incorporating thermal de-aeration of feed-water
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- Domestic Plumbing Installations (AREA)
Abstract
The present invention relates to a kind of multi-module type HTGR Nuclear Power Plant water supply system, including oxygen-eliminating device, the first pipeline, feedwater pump group, the second pipeline, high-pressure heater, the first main pipe and the pipeline of two or more the 3rd.Oxygen-eliminating device is connected with first pipeline one end, and the first pipeline other end is connected with second pipeline one end.The second pipeline other end is connected with the influent side of the first main pipe.Described 3rd pipeline one end is used to be communicated to NSSS modules, and the 3rd pipeline other end is connected with the water outlet side of the first main pipe.Feedwater pump group is arranged on the first pipeline, and high-pressure heater is arranged on second pipeline.Relative to traditional multi-module type HTGR Nuclear Power Plant water supply system, the present embodiment sets the first main pipe by increasing, high-temperature high pressure water is distributed into two or more NSSS modules by the first main pipe, so can be only with a feedwater pump group and a high-pressure heater, floor space is so just substantially reduced, and cost is relatively low.
Description
Technical field
The present invention relates to multi-module type HTGR Nuclear Power Plant technical field, more particularly to a kind of multi-module type high temperature
Air cooling reactor of nuclear power plant water supply system.
Background technology
Traditional multi-module type HTGR Nuclear Power Plant water supply system includes oxygen-eliminating device, two or more feedwater pump group and two
Individual above high-pressure heater.Feed water pump group, high-pressure heater and NSSS (Nuclear Steam Supply System, core steam
Supply system) module relative set one by one, feedwater pump group is connected with oxygen-eliminating device.Deaerated water in oxygen-eliminating device enters each feed pump
After group, feedwater pump group deaerated water is pumped into high-pressure heater, by high-pressure heater heat after deliver to NSSS modules.However,
Two or more feedwater pump group in multi-module type HTGR Nuclear Power Plant water supply system, two or more high-pressure heater cause height
Wet cold dome nuclear power station water supply system floor space is larger, and cost is higher.
The content of the invention
Based on this, it is necessary to overcome the defect of prior art to be fed water there is provided a kind of multi-module type HTGR Nuclear Power Plant
System, it enables to floor space to reduce, cost reduction.
Its technical scheme is as follows：A kind of multi-module type HTGR Nuclear Power Plant water supply system, including：Oxygen-eliminating device, first
Pipeline, feedwater pump group, the second pipeline, high-pressure heater, the first main pipe and the pipeline of two or more the 3rd；The oxygen-eliminating device and institute
State first pipeline one end to be connected, the first pipeline other end is connected with described second pipeline one end, second pipeline
The other end is connected with the influent side of first main pipe, and described 3rd pipeline one end is used to be communicated to NSSS modules, and described the
The three pipeline other ends are connected with the water outlet side of first main pipe, and the feedwater pump group is arranged on first pipeline, institute
High-pressure heater is stated to be arranged on second pipeline.
Deaerated water in above-mentioned multi-module type HTGR Nuclear Power Plant water supply system, oxygen-eliminating device is taken out by feedwater pump group
Enter to the first pipeline, after enter in the second pipeline, heat that to be converted to high temperature high by the high-pressure heater in the second pipeline
Water is pressed, enters in the first main pipe, two or more NSSS modules is delivered to one by one respectively finally by the pipeline of two or more the 3rd
In.It can be seen that, relative to traditional multi-module type HTGR Nuclear Power Plant water supply system, the present embodiment sets first by increasing
Main pipe, is distributed high-temperature high pressure water into two or more NSSS modules by the first main pipe, so can be only with a feed pump
Group and a high-pressure heater, so just substantially reduce floor space, and cost is relatively low.
In one of the embodiments, described multi-module type HTGR Nuclear Power Plant water supply system also includes hydraulic pressure tune
Regulating device, the 4th pipeline and the second main pipe being arranged between first pipeline and second pipeline, first pipeline
It is connected with the influent side of second main pipe, the water outlet side of second main pipe is connected with second pipeline, described
Four pipelines are arranged in parallel with second pipeline, and the water-pressure regulating device is arranged on the 4th pipeline；Second pipe
Isolating valve is equipped with road, the 4th pipeline.In this way, when the high-pressure heater failure on the second pipeline, control second is managed
Isolating valve on road is closed, and just no longer high-temperature high pressure water is input in the first main pipe on such second pipeline, synchronously makes the 4th
Isolating valve on pipeline is opened, and water-pressure regulating device adjusts the hydraulic pressure for the deaerated water that the 4th pipeline is inputted into the first main pipe, with
It is consistent with the hydraulic pressure for the deaerated water that the second pipeline is inputted into the first main pipe, i.e., the second pipeline is replaced by the 4th pipeline, with
When realizing that high-pressure heater breaks down, it still is able to supply deaerated water to the first main pipe, from without influenceing the deoxygenation of NSSS modules
Water supply.In the present embodiment, water-pressure regulating device uses restricting orifice.
In one of the embodiments, described multi-module type HTGR Nuclear Power Plant water supply system also includes being arranged on
The second main pipe between first pipeline and second pipeline, first pipeline and the influent side phase of second main pipe
Connection, the water outlet side of second main pipe is connected with second pipeline, and second pipeline is two or more, and described the
Two pipelines are arranged in parallel, and isolating valve is provided with second pipeline；The high-pressure heater is two or more, and the high pressure adds
Hot device and the second pipeline relative set.In this way, when NSSS modules are more, i.e., it is larger to HTHP water demand, can
So that two or more high-pressure heater carries out conversion work simultaneously, to meet the demand that NSSS modules are larger to high-temperature high pressure water
Amount；Secondly, when one of high-pressure heater failure, then the second pipeline where the high-pressure heater of failure can be will appear from
On isolating valve close, by other the second Pipeline transport high pressure-temperature water, NSSS modules work be not affected；Furthermore it is possible to
Using one of high-pressure heater as standby high-pressure heater, when determining high-pressure heater failure, then it will go out
The isolating valve on the second pipeline where the high-pressure heater of existing failure is closed, by the second pipe where standby high-pressure heater
Isolating valve on road is opened, and the high-pressure heater broken down is replaced by standby high-pressure heater, the work of NSSS modules not by
To influence.In the present embodiment, two isolating valves are provided with the second pipeline, high-pressure heater is between two isolating valves, two
After individual isolating valve close synchronously, it the operation such as just can be repaired, be changed to high-pressure heater.
In one of the embodiments, described multi-module type HTGR Nuclear Power Plant water supply system also includes being arranged on
The second main pipe between first pipeline and second pipeline, first pipeline and the influent side phase of second main pipe
Connection, the water outlet side of second main pipe is connected with second pipeline, and first pipeline is two or more, and described the
One pipeline is arranged in parallel, and the feedwater pump group is two or more, the feedwater pump group and first pipeline relative set one by one,
First pipeline is provided with isolating valve.In this way, can be synchronous by the deaerated water in oxygen-eliminating device using two or more feedwater pump group
Pump into the second main pipe, to meet demand of the NSSS modules to deaerated water.Secondly, when one of feedwater pump group failure
When, then the isolating valve that can be will appear from the first pipeline where the feedwater pump group of failure is closed, by other the first Pipeline transports
Deaerated water, NSSS modules work is not affected.For example, when the feedwater pump group of normal work is three, if one of feedwater
Pump group failure, then be only left two feedwater pump group work, then the water fluctuation of NSSS modules is 33.3% to the maximum；Normal work
When the pump group that feeds water is two, if one of feedwater pump group failure, next feedwater pump group work is only remained, then NSSS modules
Water fluctuation is 50% to the maximum.
In one of the embodiments, the feedwater pump group both sides are provided with the isolating valve, give described in one of them
Water pump group is standby feedwater pump group.In this way, when determining feedwater pump group failure, then will appear from the feedwater pump group of failure
Isolating valve on first pipeline at place is closed, and the isolating valve on the first pipeline where standby feedwater pump group is opened, by
Standby feedwater pump group replaces the feedwater pump group broken down, and the work of NSSS modules is not affected, i.e., can realize feed pump
The online switching of group, improves the availability of feedwater pump group.
In one of the embodiments, described multi-module type HTGR Nuclear Power Plant water supply system also include two with
Upper 5th pipeline and two or more first flow regulating valve, the 5th pipeline, the first flow regulating valve and described first
Pipeline relative set one by one, the first flow regulating valve is arranged on the 5th pipeline, described 5th pipeline one end and institute
State oxygen-eliminating device to be connected, the 5th pipeline other end is connected and going out positioned at the feedwater pump group with first pipeline
Water side.In this way, NSSS modules are in start-up course, the demand to water under high pressure is less than the minimum discharge of feedwater pump group, Ke Yixiang
It should increase or reduce the aperture size of first flow regulating valve, a water part for the pump group water outlet side that so feeds water can pass through the 5th
Pipeline is flow back into oxygen-eliminating device, preferable water balance effect is played, to meet the minimum discharge of feedwater pump group.The present embodiment
In, first flow regulating valve both sides are provided with isolating valve.
In one of the embodiments, it is provided with second flow regulating valve on second pipeline.Second flow regulating valve
The uninterrupted that the high-temperature high pressure water in the second pipeline is entered in NSSS modules can be adjusted.
In one of the embodiments, second flow regulating valve set on second pipeline is two, two institutes
Second flow regulating valve is stated to be arranged in parallel, and the second flow regulating valve both sides are provided with isolating valve.In this way, ought wherein one
During individual second flow regulating valve failure, another second flow regulating valve can be used, NSSS modules work not by shadow
Ring.
In one of the embodiments, it is provided with check-valves on first pipeline.Check-valves can avoid the pump group that feeds water
Outlet water under high pressure be back in oxygen-eliminating device.
In one of the embodiments, filter screen is provided with first pipeline, and the filter screen is located at the feed pump
The water inlet side of group.Filter screen can filter out the impurity mixed in deaerated water, the deaerated water that raising is entered in feedwater pump group
Degree of purity.
Brief description of the drawings
Fig. 1 is the multi-module type HTGR Nuclear Power Plant water supply system structural representation one described in the embodiment of the present invention；
Fig. 2 is the multi-module type HTGR Nuclear Power Plant water supply system structural representation two described in the embodiment of the present invention；
Fig. 3 is the multi-module type HTGR Nuclear Power Plant water supply system structural representation three described in the embodiment of the present invention；
Fig. 4 is the multi-module type HTGR Nuclear Power Plant water supply system structural representation four described in the embodiment of the present invention；
Fig. 5 is the multi-module type HTGR Nuclear Power Plant water supply system structural representation five described in the embodiment of the present invention；
Fig. 6 is the multi-module type HTGR Nuclear Power Plant water supply system structural representation six described in the embodiment of the present invention.
10th, oxygen-eliminating device, the 20, first pipeline, 21, feedwater pump group, 22, check-valves, 23, filter screen, the 30, second pipeline, 31, high
Press heater, 32, second flow regulating valve, the 40, first main pipe, the 50, the 3rd pipeline, 60, NSSS modules, the 70, the 4th pipeline,
71st, water-pressure regulating device, the 80, second main pipe, the 90, the 5th pipeline, 91, first flow regulating valve, 100, isolating valve.
Embodiment
In order to facilitate the understanding of the purposes, features and advantages of the present invention, below in conjunction with the accompanying drawings to the present invention
Embodiment be described in detail.Many details are elaborated in the following description to fully understand this hair
It is bright.But the invention can be embodied in many other ways as described herein, those skilled in the art can be not
Similar improvement is done in the case of running counter to intension of the present invention, therefore the present invention is not limited by following public specific embodiment.
In the description of the invention, it is to be understood that term " first ", " second " are only used for describing purpose, and can not
It is interpreted as indicating or implies relative importance or the implicit quantity for indicating indicated technical characteristic.Thus, define " the
One ", at least one this feature can be expressed or be implicitly included to the feature of " second ".In the description of the invention, " multiple "
It is meant that at least two, such as two, three etc., unless otherwise specifically defined.
, can be with when an element is considered as " connection " another element it should be noted that in embodiment described above
It is directly to another element or may be simultaneously present intermediary element.On the contrary, when element for be referred to as " direct " with it is another
When element is connected, in the absence of intermediary element.
As shown in Figures 1 to 6, a kind of multi-module type HTGR Nuclear Power Plant water supply system, including oxygen-eliminating device 10, first
Pipeline 20, feedwater pump group 21, the second pipeline 30, high-pressure heater 31, the first main pipe 40 and the pipeline 50 of two or more the 3rd.Institute
Oxygen-eliminating device 10 is stated with described one end of first pipeline 20 to be connected.The other end of first pipeline 20 and described one end of second pipeline 30
It is connected.The other end of second pipeline 30 is connected with the influent side of first main pipe 40.Described one end of 3rd pipeline 50
For being communicated to NSSS modules 60, the other end of the 3rd pipeline 50 is connected with the water outlet side of first main pipe 40.It is described
Feedwater pump group 21 is arranged on first pipeline 20, and the high-pressure heater 31 is arranged on second pipeline 30.
Deaerated water in above-mentioned multi-module type HTGR Nuclear Power Plant water supply system, oxygen-eliminating device 10 is by feedwater pump group
21 be pumped into the first pipeline 20, after enter in the second pipeline 30, heated by the high-pressure heater 31 in the second pipeline 30
High-temperature high pressure water is converted to, is entered in the first main pipe 40, is delivered to one by one respectively finally by the pipeline 50 of two or more the 3rd
In two or more NSSS modules 60.It can be seen that, relative to traditional multi-module type HTGR Nuclear Power Plant water supply system, this implementation
Example sets the first main pipe 40 by increasing, and is distributed high-temperature high pressure water into two or more NSSS modules 60 by the first main pipe 40,
So it so can just substantially reduce floor space only with an a feedwater pump group 21 and high-pressure heater 31, and into
This is relatively low.
In the present embodiment, described multi-module type HTGR Nuclear Power Plant water supply system also includes water-pressure regulating device
71st, the 4th pipeline 70 and the second main pipe 80 being arranged between first pipeline 20 and second pipeline 30.Described first
Pipeline 20 is connected with the influent side of second main pipe 80.The water outlet side of second main pipe 80 and the phase of the second pipeline 30
Connection, the 4th pipeline 70 is arranged in parallel with second pipeline 30, and the water-pressure regulating device 71 is arranged on the described 4th
On pipeline 70.Isolating valve 100 is equipped with second pipeline 30, the 4th pipeline 70.In this way, when on the second pipeline 30
During 31 failure of high-pressure heater, the isolating valve 100 on the second pipeline 30 of control is closed, just no longer by height on such second pipeline 30
Warm water under high pressure is input in the first main pipe 40, synchronously opens the isolating valve 100 on the 4th pipeline 70, and water-pressure regulating device 71 is adjusted
The hydraulic pressure for the deaerated water that whole 4th pipeline 70 is inputted into the first main pipe 40, to be inputted with the second pipeline 30 into the first main pipe 40
Deaerated water hydraulic pressure it is consistent, i.e., by the 4th pipeline 70 replace the second pipeline 30, with realize high-pressure heater 31 occur therefore
During barrier, it still is able to supply deaerated water to the first main pipe 40, from without influenceing the deoxygenation water supply of NSSS modules 60.The present embodiment
In, water-pressure regulating device 71 uses restricting orifice.
In addition, referring to Fig. 2, Fig. 3 and Fig. 5, described multi-module type HTGR Nuclear Power Plant water supply system also includes
It is arranged on the second main pipe 80 between first pipeline 20 and second pipeline 30.First pipeline 20 and described second
The influent side of main pipe 80 is connected, and the water outlet side of second main pipe 80 is connected with second pipeline 30, second pipe
Road 30 is two or more, and second pipeline 30 is arranged in parallel, and isolating valve 100 is provided with second pipeline 30；It is described
High-pressure heater 31 is two or more, the high-pressure heater 31 and the relative set of the second pipeline 30.In this way, when NSSS moulds
It is when block 60 is more, i.e., larger to HTHP water demand, two or more high-pressure heater 31 can be made while carrying out conversion work
Make, to meet the demand that NSSS modules 60 are larger to high-temperature high pressure water；Secondly, when one of failure of high-pressure heater 31
When, then the isolating valve 100 that can be will appear from the second pipeline 30 where the high-pressure heater 31 of failure is closed, by other second
The conveying high-pressure high-temperature water of pipeline 30, NSSS modules 60 work and are not affected；Furthermore it is possible to by one of high-pressure heater 31
As standby high-pressure heater 31, when determining the failure of high-pressure heater 31, then the hyperbaric heating of failure will appear from
The isolating valve 100 on the second pipeline 30 where device 31 is closed, by the second pipeline 30 where standby high-pressure heater 31
Isolating valve 100 open, the high-pressure heater 31 of failure is replaced by standby high-pressure heater 31, NSSS modules 60 work
It is not affected.In the present embodiment, be provided with two isolating valves 100 on the second pipeline 30, high-pressure heater 31 be in two every
From between valve 100, after two close synchronouslies of isolating valve 100, it the operation such as just can be repaired, be changed to high-pressure heater 31.
In addition, referring to Fig. 4 to Fig. 6, described multi-module type HTGR Nuclear Power Plant water supply system also includes setting
The second main pipe 80 between first pipeline 20 and second pipeline 30.First pipeline 20 and second main pipe
80 influent side is connected, and the water outlet side of second main pipe 80 is connected with second pipeline 30.First pipeline 20
For two or more, and first pipeline 20 is arranged in parallel.It is described feedwater pump group 21 be two or more, the feedwater pump group 21 with
First pipeline 20 relative set one by one.First pipeline 20 is provided with isolating valve 100.In this way, can use two with
Upper feedwater pump group 21 is synchronous to pump the deaerated water in oxygen-eliminating device 10 into the second main pipe 80, to meet NSSS modules 60 to deoxygenation
The demand of water.Secondly, when one of feedwater 21 failure of pump group, then the place of feedwater pump group 21 of failure can be will appear from
Isolating valve 100 on first pipeline 20 is closed, and deaerated water is conveyed by other first pipelines 20, and NSSS modules 60 work not by shadow
Ring.For example, when the feedwater pump group 21 of normal work is three, if one of feedwater failure of pump group 21, is only left two and gives
Water pump group 21 works, then the water fluctuation of NSSS modules 60 is 33.3% to the maximum；When the feedwater pump group 21 of normal work is two,
If one of feedwater failure of pump group 21, only remain next feedwater pump group 21 and work, then the water of NSSS modules 60 is fluctuated most
Greatly 50%.
Further, feedwater pump group 21 both sides are provided with the isolating valve 100, one of them described feedwater pump group
21 be standby feedwater pump group 21.In this way, when determining the feedwater failure of pump group 21, then will appear from the feedwater pump group of failure
The isolating valve 100 on the first pipeline 20 where 21 is closed, by first pipeline 20 at the standby place of feedwater pump group 21 every
Opened from valve 100, the feedwater pump group 21 of failure is replaced by standby feedwater pump group 21, NSSS modules 60 work not by shadow
Ring, i.e., can realize that feedwater pump group 21 switches online, improve the availability of feedwater pump group 21..
In the present embodiment, Fig. 5 and Fig. 6 are referred to, described multi-module type HTGR Nuclear Power Plant water supply system is also wrapped
Include the pipeline 90 of two or more the 5th and two or more first flow regulating valve 91.5th pipeline 90, the first flow are adjusted
Save valve 91 and first pipeline 20 relative set one by one.The first flow regulating valve 91 is arranged on the 5th pipeline 90
On.Described one end of 5th pipeline 90 is connected with the oxygen-eliminating device 10, the other end of the 5th pipeline 90 and first pipeline
20 are connected and positioned at the water outlet side of the feedwater pump group 21.In this way, NSSS modules 60 are in start-up course, to water under high pressure
Demand is less than the minimum discharge of feedwater pump group 21, accordingly can increase or reduce the aperture size of first flow regulating valve 91,
A water part for so feedwater water outlet side of pump group 21 can be flow back into oxygen-eliminating device 10 by the 5th pipeline 90, play preferable water
Balanced action is measured, to meet the minimum discharge of feedwater pump group 21.In the present embodiment, the both sides of first flow regulating valve 91 are provided with
Isolating valve 100.
In addition, being provided with second flow regulating valve 32 on second pipeline 30.Second flow regulating valve 32 can be adjusted
The uninterrupted that high-temperature high pressure water in second pipeline 30 is entered in NSSS modules 60.
Further, second flow regulating valve 32 set on second pipeline 30 is two, two described second
Flow control valve 32 is arranged in parallel, and the both sides of second flow regulating valve 32 are provided with isolating valve 100.In this way, ought be wherein
During one second flow 32 failure of regulating valve, another second flow regulating valve 32 can be used, NSSS modules 60 work
It is not affected.
Further, it is provided with check-valves 22 on first pipeline 20.Check-valves 22 can avoid the pump group 21 that feeds water
Outlet water under high pressure is back in oxygen-eliminating device 10.
Further, filter screen 23 is provided with first pipeline 20, and the filter screen 23 is located at the feedwater pump group 21
Water inlet side.Filter screen 23 can filter out the impurity mixed in deaerated water, improve the deaerated water entered in feedwater pump group 21
Degree of purity.
Each technical characteristic of embodiment described above can be combined arbitrarily, to make description succinct, not to above-mentioned reality
Apply all possible combination of each technical characteristic in example to be all described, as long as however, the combination of these technical characteristics is not deposited
In contradiction, the scope of this specification record is all considered to be.
Embodiment described above only expresses the several embodiments of the present invention, and it describes more specific and detailed, but simultaneously
Can not therefore it be construed as limiting the scope of the patent.It should be pointed out that coming for one of ordinary skill in the art
Say, without departing from the inventive concept of the premise, various modifications and improvements can be made, these belong to the protection of the present invention
Scope.Therefore, the protection domain of patent of the present invention should be determined by the appended claims.
Claims (10)
1. a kind of multi-module type HTGR Nuclear Power Plant water supply system, it is characterised in that including：Oxygen-eliminating device, the first pipeline, give
Water pump group, the second pipeline, high-pressure heater, the first main pipe and the pipeline of two or more the 3rd；The oxygen-eliminating device and the described first pipe
Road one end is connected, and the first pipeline other end is connected with described second pipeline one end, the second pipeline other end with
The influent side of first main pipe is connected, and described 3rd pipeline one end is used to be communicated to NSSS modules, and the 3rd pipeline is another
One end is connected with the water outlet side of first main pipe, and the feedwater pump group is arranged on first pipeline, and the high pressure adds
Hot device is arranged on second pipeline.
2. multi-module type HTGR Nuclear Power Plant water supply system according to claim 1, it is characterised in that also including water
Press adjusting means, the 4th pipeline and the second main pipe being arranged between first pipeline and second pipeline, described first
Pipeline is connected with the influent side of second main pipe, and the water outlet side of second main pipe is connected with second pipeline, institute
State the 4th pipeline to be arranged in parallel with second pipeline, the water-pressure regulating device is arranged on the 4th pipeline；Described
Isolating valve is equipped with two pipelines, the 4th pipeline.
3. multi-module type HTGR Nuclear Power Plant water supply system according to claim 1, it is characterised in that also including setting
Put the second main pipe between first pipeline and second pipeline, first pipeline and the water inlet of second main pipe
Side is connected, and the water outlet side of second main pipe is connected with second pipeline, and second pipeline is two or more, and institute
State the second pipeline to be arranged in parallel, isolating valve is provided with second pipeline；The high-pressure heater is two or more, the height
Press heater and the second pipeline relative set.
4. multi-module type HTGR Nuclear Power Plant water supply system according to claim 1, it is characterised in that also including setting
Put the second main pipe between first pipeline and second pipeline, first pipeline and the water inlet of second main pipe
Side is connected, and the water outlet side of second main pipe is connected with second pipeline, and first pipeline is two or more, and institute
State the first pipeline to be arranged in parallel, the feedwater pump group is two or more, and the feedwater pump group is corresponding one by one to first pipeline
Set, first pipeline is provided with isolating valve.
5. multi-module type HTGR Nuclear Power Plant water supply system according to claim 4, it is characterised in that the feedwater
Pump group both sides are provided with the isolating valve, and one of them described feedwater pump group is standby feedwater pump group.
6. multi-module type HTGR Nuclear Power Plant water supply system according to claim 4, it is characterised in that also including two
5th pipeline and two or more first flow regulating valve more than individual, the 5th pipeline, the first flow regulating valve and described
First pipeline relative set one by one, the first flow regulating valve is arranged on the 5th pipeline, described 5th pipeline one end
It is connected with the oxygen-eliminating device, the 5th pipeline other end is connected with first pipeline and positioned at the feedwater pump group
Water outlet side.
7. multi-module type HTGR Nuclear Power Plant water supply system according to claim 1, it is characterised in that described second
Second flow regulating valve is provided with pipeline.
8. multi-module type HTGR Nuclear Power Plant water supply system according to claim 7, it is characterised in that described second
Set second flow regulating valve is two on pipeline, and two second flow regulating valves are arranged in parallel, and described second
Flow control valve both sides are provided with isolating valve.
9. multi-module type HTGR Nuclear Power Plant water supply system according to claim 1, it is characterised in that described first
Check-valves is provided with pipeline.
10. the multi-module type HTGR Nuclear Power Plant water supply system according to any one of claim 1 to 9, its feature exists
In, filter screen is provided with first pipeline, and the filter screen is located at the water inlet side of the feedwater pump group.
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|---|---|---|---|---|
| RU2097846C1 (en) * | 1996-04-26 | 1997-11-27 | Ленинградская атомная электростанция им.В.И.Ленина | Method for cooling fuel assemblies in case of coolant failure in circulating circuit |
| CN202484973U (en) * | 2012-02-20 | 2012-10-10 | 江苏核电有限公司 | Water supply system of steam generator |
| CN202948744U (en) * | 2012-10-22 | 2013-05-22 | 中国核动力研究设计院 | Water supply system adopting once-through steam generator reactor |
| JP2014137171A (en) * | 2013-01-16 | 2014-07-28 | Toshiba Corp | Water hammer prevention method of water supply heater pipeline |
| CN104934080A (en) * | 2015-06-26 | 2015-09-23 | 上海核工程研究设计院 | Main water supply system of double-reactor nuclear power station |
-
2017
- 2017-04-26 CN CN201710283154.XA patent/CN107131494B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2097846C1 (en) * | 1996-04-26 | 1997-11-27 | Ленинградская атомная электростанция им.В.И.Ленина | Method for cooling fuel assemblies in case of coolant failure in circulating circuit |
| CN202484973U (en) * | 2012-02-20 | 2012-10-10 | 江苏核电有限公司 | Water supply system of steam generator |
| CN202948744U (en) * | 2012-10-22 | 2013-05-22 | 中国核动力研究设计院 | Water supply system adopting once-through steam generator reactor |
| JP2014137171A (en) * | 2013-01-16 | 2014-07-28 | Toshiba Corp | Water hammer prevention method of water supply heater pipeline |
| CN104934080A (en) * | 2015-06-26 | 2015-09-23 | 上海核工程研究设计院 | Main water supply system of double-reactor nuclear power station |
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| CN107131494B (en) | 2019-03-12 |
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