CN104879737A - Secondary side isolation method of steam generator in million-kilowatt-class pressurized water reactor nuclear power station - Google Patents
Secondary side isolation method of steam generator in million-kilowatt-class pressurized water reactor nuclear power station Download PDFInfo
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Abstract
The invention relates to the technical field of nuclear power, and provides a secondary side isolation method of steam generator in a million-kilowatt-class pressurized water reactor nuclear power station. The method comprises the following steps: blocking a main steam system; blocking at a steam outlet current limiter between the steam generator and the main steam system; blocking a water supply system; injecting water into a connecting pipeline of the main water supply system and the steam generator to performing sealing isolation; injecting water into a connecting pipeline of an auxiliary water supply and the steam generator to perform sealing isolation; blocking a drainage system; blocking at a current limiter part in the drainage system connected with the steam generator; closing the valve; fully closing a boundary valve which is communicated with the secondary side of the steam generator. Through the steps, good air-tightness of the secondary side of the steam generator is guaranteed, and full isolation of the secondary side of the steam generator is realized.
Description
Technical field
The present invention relates to technical field of nuclear power, more particularly, relate to steam generator secondary side partition method in kilowatt pressurized water reactor nuclear power station.
Background technology
Nuclear steam generator SG (steam generator) is one of three large equipments in million kilowatt presurized water reactor nuclear island, it is the border of PWR nuclear power plant primary Ioops, secondary circuit, the heat that reactor produces is passed to steam generator secondary side by it, and the steam of generation promotes steam turbine generator generating after the drying of I and II steam-water separator.Steam generator is connected with reactor pressure vessel, not only directly affects power and the efficiency in power station, and when carrying out exchange heat, also plays a part to intercept radioactivity catalyst carrier, most important to nuclear plant safety.
Particularly, in pressurized-water reactor nuclear power plant, steam generator the heat in primary Ioops cooling agent is passed to secondary circuit feedwater, make its produce saturated vapor supply secondary circuit in power set.Each loop is equipped with a steam generator, and every platform capacity is according to the heat output of reactor design of transmitting 1/3rd during Operation at full power.As the equipment connecting primary Ioops and secondary circuit, steam generator forms the second protective barrier preventing radioactivity from leaking between two loops.Because water may damagedly leak by activation after irradiation and a small amount of fuel can, the primary Ioops cool stream flowing through reactor core has radioactivity, and Secondary Circuit of PWR equipment can not be subject to radioactive pollution, and the tube sheet of steam generator and inverted U-shaped pipe are the parts of reactor coolant pressure boundary, belong to one of second radioactivity protection barrier.
As shown in Figure 1, it is made up of lower member (evaporator section) and upper component (carbonated drink segregation section) two large divisions the current steam generator contour structures for nuclear power station.Lower member mainly contains: low head, tube sheet, bottom shell ring, U-shaped heat-transfer pipe, tube bank sleeve, supporting clapboard etc.; Upper component mainly contains: primary separator, second-stage separator, feedwater endless tube, current limiter, upper cover and top shell ring etc.The primary side of steam generator is exactly that side component from flowing through after the cooling agent that reactor pressure vessel comes enters steam generator, i.e. corresponding above-mentioned lower member; Secondary side is heated in water supply loop and is produced that side component of steam, i.e. corresponding above-mentioned upper component.But tube sheet and heat-transfer pipe are while be primary side, and another side is secondary side.From nuclear safety classification, the parts of primary side belong to nuclear safety 1 grade, and the parts of secondary side belong to nuclear safety 2 grades.
According to the requirement of French specification RST-M97 version (2000), nuclear power generating sets must implement the test of steam generator heat-transfer pipe 100% helium mass spectrum leak detection when each Ten-year outage.This test is carried out after Primary hydraulic test terminates, and forms an entirety with Primary hydraulic test, the full eddy current inspection of steam generator heat-transfer pipe, and grasp the health status of steam generator heat-transfer pipe, this is conducive to the safe operation of unit comprehensively.At run duration, when primary side of steam generator to the slip of secondary side more than 5L/H, must helium test for leak be carried out.
Steam generator heat-transfer pipe helium mass spectrum leak detection is filled with search gas-helium to steam generator secondary side, and keep the pressure of 6bar, leakage channel may be there is to make helium by heat-transfer pipe and enter primary side, at the opposite side of inwall, search gas is collected, and utilize helium mass analyzer to detect, to determine existence and the size of leakage.
In helium mass spectrum leak detection test, complete first and second side clean, emptying after, need the secondary side of steam generator to isolate, to avoid the gas loss be filled with in follow-up test.Steam generator secondary side bounds is larger, it is connected with VVP (main steam system), ARE (main feed system), ASG (auxiliary feedwater system), APG (drainage), GCT (bypass discharge leg system), REN (core sampler), SIR (chemical reagent injecting systems), the main isolation of steam generator secondary side of standard cannot meet the requirement of sealing, particularly ARE, ASG, APG and VVP system.The sealing of steam generator secondary side isolation boundary is the key of helium mass spectrum leak detection test, if steam generator secondary side can not keep the pressure of 6bar, helium mass spectrum leak detection test cannot be implemented.Existing isolation method is generally the valve by closing each passage be communicated with steam generator, steam generator is isolated, but the isolation effect of this kind of method is not fine, poor air-tightness, the follow-up result of the test degree of accuracy and sensitivity tool are had a certain impact, therefore needs a kind of new partition method of searching badly and solve this problem.
Summary of the invention
The object of the present invention is to provide steam generator secondary side partition method in a kind of kilowatt pressurized water reactor nuclear power station, be intended to solve in prior art the problem that the steam generator secondary side poor air-tightness, the isolation effect that exist are bad.
For solving the problems of the technologies described above, technical scheme of the present invention is: provide steam generator secondary side partition method in a kind of kilowatt pressurized water reactor nuclear power station, comprise the following steps:
Main steam system shutoff step: by the steam (vapor) outlet current limiter place's shutoff between steam generator and main steam system;
Water supply system shutoff step: and in the connecting pipe of main feed system and steam generator, inject water carry out seal isolation; And in the connecting pipe of auxiliary feedwater system and steam generator, inject water carry out seal isolation;
Drainage shutoff step: the current limiter place in the drainage be connected with steam generator is carried out shutoff; Valve closing step: by the border valve Close All through with steam generator secondary side.
Alternatively, in described main steam system shutoff step, guillotine blocking is adopted to carry out shutoff to described steam (vapor) outlet current limiter.
Alternatively, when adopting guillotine blocking to carry out shutoff, guillotine is filled in the steam pod apertures at steam generator top.
Alternatively, after guillotine being filled in the steam pod apertures at steam generator top, guarantee that the sealing ring of guillotine blocking plane and steam pod apertures inwall contact completely with inletpiston and compress.
Alternatively, in water supply system shutoff step, in the connecting pipe to main feed system and steam generator, inject water when carrying out seal isolation, inject water and be introduced into horizontal pipe, then enter vertical pipeline, and in vertical pipeline, reach the first preset water level height; In the connecting pipe to auxiliary feedwater system and steam generator, inject water when carrying out seal isolation, inject water and be introduced into horizontal pipe, then enter vertical pipeline, and in vertical pipeline, reach the second preset water level height.
Alternatively, in water supply system shutoff step, the vertical pipeline middle water level of main feed system is monitored, when water level is lower than the first preset water level height, in the horizontal pipe of main feed system, inject water until reach the first preset water level height; The vertical pipeline middle water level of auxiliary feedwater system is monitored, when water level is lower than the second preset water level height, in the horizontal pipe of auxiliary feedwater system, injects water until reach the first preset water level height.
Alternatively, in water supply system shutoff step, the first level sensor is set in the vertical pipeline of main feed system, utilizes the water level in described first level sensor monitoring vertical pipeline; Second level sensor is set in the vertical pipeline of auxiliary feedwater system, utilizes the water level in described second level sensor monitoring vertical pipeline.
Alternatively, in drainage shutoff step, blocking is utilized to carry out shutoff to the current limiter in drainage.Alternatively, in drainage shutoff step, adopt blank flange to replace described current limiter and carry out shutoff.
Alternatively, in drainage shutoff step, adopt end socket, pipe cap or plug to replace described current limiter and carry out shutoff.In the present invention, by above-mentioned steps, ensure the good air-tightness of steam generator secondary side, realize the completely isolated of steam generator secondary side in kilowatt pressurized water reactor nuclear power station.
Accompanying drawing explanation
Fig. 1 is the connection diagram of steam generator and main feed system and auxiliary feedwater system in nuclear power station in the embodiment of the present invention.
Detailed description of the invention
In order to make object of the present invention, technical scheme and advantage clearly understand, below in conjunction with drawings and Examples, the present invention is further elaborated.Should be appreciated that specific embodiment described herein only in order to explain the present invention, be not intended to limit the present invention.
It should be noted that, when element is called as " being fixed on " or " being arranged at " another element, it can directly on another element or may there is centering elements simultaneously.When an element is called as " being connected to " another element, it can be directly connected to another element or may there is centering elements simultaneously.
Also it should be noted that, the orientation term such as left and right, upper and lower in the present embodiment, is only relative concept or be reference with the normal operating condition of product each other, and should not be regarded as have restrictive.
In nuclear power station provided by the invention, steam generator secondary side partition method comprises the following steps:
Main steam system shutoff step;
Water supply system shutoff step;
Drainage shutoff step;
Valve closing step.
Without sequencing between above steps, also can carry out simultaneously.
In main steam system shutoff step, mainly by the steam (vapor) outlet current limiter place's shutoff between steam generator and main steam system.Particularly, the function of main steam system is that the steam that steam generator produces is delivered to main steam turbine and auxiliary equipment (as steam turbine gland system, condenser and separator, steam by-pass system, auxiliary feed water pump steam turbine etc.) thereof.Main steam system is by three main steam pipes, and every root pipeline is connected with a steam generator outlet respectively.And between steam generator and main steam system, be provided with steam (vapor) outlet current limiter, adopt special being blocked in be arranged on this and to carry out shutoff to passage therebetween.
Preferably, special blocking is guillotine blocking.When adopting guillotine blocking to carry out shutoff, guillotine is filled in the steam pod apertures at steam generator top, and guarantee that the sealing ring of guillotine blocking plane and steam pod apertures inwall contact completely with inletpiston and compress, like this, it is solid and reliable that the blocking of guarantee guillotine is installed.
Particularly, when guillotine blocking is installed, first need the drier removing steam generator secondary side top, then establish cover plate on U-Shaped Tube for PWR Steam Generator overhead vapor outlet tube sheet upper berth, prevent foreign matter from falling into inside; And check that whether steam generator overhead vapor pod apertures plane is smooth, check whether pod apertures inside has penetrability cut, check whether pod apertures inside has burn into foreign matter, clears up in time if necessary; Then check that whether the annex of guillotine blocking is complete, whether guillotine plug for seal rubber column surface has cut, is then filled in the steam pod apertures at steam generator top by guillotine.Stop after needing to adopt special spanner that its clockwise is rotated multi-turn when mounted.Steam generator top has seven pod apertures, and the guillotine blocking installation method at each pod apertures place is the same.
When after the off-test of steam generator helium mass spectrum leak detection, need to remove guillotine blocking, now, first depleted of steam generator interior media, by the inner oxygen content of oxygen table monitoring steam generator before work, prevent from suffocating during dismounting, need to buttress guillotine blocking in unloading process, whether in order to avoid guillotine blocking is fallen, guillotine blocking being taken off the upper annex of rear inspection guillotine blocking has disappearance.According to same method, the guillotine blocking of seven, steam generator top is all taken off.
In above-mentioned water supply system shutoff step: the valve between main feed system and steam generator is non-return valve, and non-return valve is closed automatically, close in the connecting pipe of backward main feed system and steam generator and inject water and carry out seal isolation; Meanwhile, the non-return valve between auxiliary feedwater system and steam generator is also closed automatically, injects water and carry out seal isolation in the connecting pipe of auxiliary feedwater system and steam generator.This is because main feed system, the valve arranged between auxiliary feedwater system and steam generator are non-return valve, so good sealing effectiveness can not be reached only by the mode of closing non-return valve, Bound moisture is therefore needed to seal.Fig. 1 is the connection diagram of steam generator 10 and main feed system 20 and auxiliary feedwater system 30.The connecting pipe 40 that main feed system 20 and auxiliary feedwater system 30 lead to steam generator 10 includes two sections: the vertical pipeline 41 be directly communicated with steam generator 10 and the horizontal pipe 42 be connected with vertical pipeline 41, and each horizontal pipe 42 is respectively equipped with two water inlets 421, water can be injected in the mode of two water inlet 421 place water service pipes by scene.When injecting water and carry out seal isolation in main feed system 20 and the connecting pipe 40 of steam generator 10, inject water and be introduced into horizontal pipe 42, then enter vertical pipeline, and in vertical pipeline, reach the first preset water level height; In the connecting pipe to auxiliary feedwater system and steam generator, inject water when carrying out seal isolation, inject water and be introduced into horizontal pipe 42, then enter vertical pipeline 41, and in vertical pipeline 41, reach the second preset water level height.Herein, the first preset water level height and the second preset water level height can be the same or different, and preset water level actual height can be determined by the actual situation.
Further, sealing due to pipe downstream valve is not good especially, the water injecting connecting pipe 40 slowly may ooze out along with the prolongation of time, therefore water level monitoring system is set in connecting pipe 40, when vertical pipeline 41 middle water level monitoring main feed system 20 is lower than the first preset water level height, then inject water until reach the first preset water level height in the horizontal pipe 42 of main feed system 20; If water level remain on the first preset water level height or higher than this height time, can without water filling; Same, vertical pipeline 41 middle water level of water level monitoring system to auxiliary feedwater system 30 is utilized to monitor, when water level is lower than the second preset water level height, water is injected until reach the first preset water level height in the horizontal pipe 42 of auxiliary feedwater system, if water level remain on the second preset water level height or higher than this height time, can without water filling.
Particularly, water level monitoring system comprises the first level sensor (not shown) be arranged in the vertical pipeline 41 of main feed system 20, utilizes the water level in the first level sensor monitoring vertical pipeline 41; Water level monitoring system also comprises in the vertical pipeline 41 being arranged on auxiliary feedwater system 30 and arranges the second level sensor (not shown), utilizes the water level in the second level sensor monitoring vertical pipeline 41.Water level monitoring system can also comprise the warning system be connected with the first level sensor and the second level sensor, utilizes warning system to carry out alert and carries out water flood operations; Or, first level sensor and the second level sensor are connected with a controller respectively, this controller can control the break-make injecting switch simultaneously, like this, when water level is lower than preset water level height, first level sensor or the second level sensor respectively by signal feedback to controller, water filling switch opens is carried out water filling by controller.
In drainage shutoff step: mainly by the current limiter place shutoff in the drainage that is connected with steam generator.Particularly, current limiter is restricting orifice.Preferably, adopt blank flange to replace restricting orifice and carry out shutoff.Blank flange is the totally enclosed flange of middle atresia, can play good isolation, cutting action.And blank flange good seal performance, for needing completely isolated system, can be used as reliable isolating means.Certainly, adopting other method for blocking, as directly adopted blocking to carry out shutoff to current limiter, or adopting the alternative blank flanges such as end socket, pipe cap, welding plug to carry out shutoff also within protection scope of the present invention.
In valve closing step: by the border valve Close All through with steam generator secondary side.Specifically also comprise the border valve Close All with GCT (bypass discharge leg system), REN (core sampler) and SIR (chemical reagent injecting systems).
By the operation of above steps, ensure the air-tightness that steam generator secondary side is good to realize steam generator secondary side completely isolated.
These are only preferred embodiment of the present invention, not in order to limit the present invention, all any amendments done within the spirit and principles in the present invention, equivalent replacement and improvement etc., all should be included within protection scope of the present invention.
Claims (10)
1. a steam generator secondary side partition method in kilowatt pressurized water reactor nuclear power station, is characterized in that, comprise the following steps:
Main steam system shutoff step: by the steam (vapor) outlet current limiter place's shutoff between steam generator and main steam system;
Water supply system shutoff step: inject water and carry out seal isolation in the connecting pipe of main feed system and steam generator; And in the connecting pipe of auxiliary feedwater system and steam generator, inject water carry out seal isolation;
Drainage shutoff step: the current limiter place in the drainage be connected with steam generator is carried out shutoff; Valve closing step: by the border valve Close All through with steam generator secondary side.
2. steam generator secondary side partition method in kilowatt pressurized water reactor nuclear power station as claimed in claim 1, is characterized in that, in described main steam system shutoff step, adopts guillotine blocking to carry out shutoff to described steam (vapor) outlet current limiter.
3. steam generator secondary side partition method in kilowatt pressurized water reactor nuclear power station as claimed in claim 2, is characterized in that, when adopting guillotine blocking to carry out shutoff, is filled in the steam pod apertures at steam generator top by guillotine.
4. steam generator secondary side partition method in kilowatt pressurized water reactor nuclear power station as claimed in claim 3, it is characterized in that, after guillotine being filled in the steam pod apertures at steam generator top, guarantee that the sealing ring of guillotine blocking plane and steam pod apertures inwall contact completely with inletpiston and compress.
5. steam generator secondary side partition method in kilowatt pressurized water reactor nuclear power station as claimed in claim 1, it is characterized in that, in water supply system shutoff step, water is injected when carrying out seal isolation in the connecting pipe to main feed system and steam generator, inject water and be introduced into horizontal pipe, enter vertical pipeline again, and in vertical pipeline, reach the first preset water level height; In the connecting pipe to auxiliary feedwater system and steam generator, inject water when carrying out seal isolation, inject water and be introduced into horizontal pipe, then enter vertical pipeline, and in vertical pipeline, reach the second preset water level height.
6. steam generator secondary side partition method in kilowatt pressurized water reactor nuclear power station as claimed in claim 5, it is characterized in that, in water supply system shutoff step, the vertical pipeline middle water level of main feed system is monitored, when water level is lower than the first preset water level height, in the horizontal pipe of main feed system, inject water until reach the first preset water level height; The vertical pipeline middle water level of auxiliary feedwater system is monitored, when water level is lower than the second preset water level height, in the horizontal pipe of auxiliary feedwater system, injects water until reach the first preset water level height.
7. steam generator secondary side partition method in kilowatt pressurized water reactor nuclear power station as claimed in claim 6, it is characterized in that, in water supply system shutoff step, first level sensor is set in the vertical pipeline of main feed system, utilizes the water level in described first level sensor monitoring vertical pipeline; Second level sensor is set in the vertical pipeline of auxiliary feedwater system, utilizes the water level in described second level sensor monitoring vertical pipeline.
8. steam generator secondary side partition method in kilowatt pressurized water reactor nuclear power station as claimed in claim 1, is characterized in that, in drainage shutoff step, utilizes blocking to carry out shutoff to the current limiter in drainage.
9. steam generator secondary side partition method in kilowatt pressurized water reactor nuclear power station as claimed in claim 1, is characterized in that, in drainage shutoff step, adopts blank flange to replace described current limiter and carries out shutoff.
10. steam generator secondary side partition method in kilowatt pressurized water reactor nuclear power station as claimed in claim 1, is characterized in that, in drainage shutoff step, adopts end socket, pipe cap or plug to replace described current limiter and carries out shutoff.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107289436A (en) * | 2016-03-31 | 2017-10-24 | 华北电力大学 | It is a kind of that there is the support flow-guiding structure for improving steam generator heat exchange efficiency |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5895239A (en) * | 1981-12-01 | 1983-06-06 | Toshiba Corp | Monitoring device for leakage of valve |
| EP0146305A2 (en) * | 1983-12-19 | 1985-06-26 | The Babcock & Wilcox Company | Controlling leaks between primary and secondary circuits of a steam generator of a pressurised water reactor system |
| CN202736508U (en) * | 2012-08-22 | 2013-02-13 | 中广核工程有限公司 | Emergency water injection system of secondary side of nuclear power plant |
-
2015
- 2015-05-20 CN CN201510259985.4A patent/CN104879737B/en active Active
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5895239A (en) * | 1981-12-01 | 1983-06-06 | Toshiba Corp | Monitoring device for leakage of valve |
| EP0146305A2 (en) * | 1983-12-19 | 1985-06-26 | The Babcock & Wilcox Company | Controlling leaks between primary and secondary circuits of a steam generator of a pressurised water reactor system |
| CN202736508U (en) * | 2012-08-22 | 2013-02-13 | 中广核工程有限公司 | Emergency water injection system of secondary side of nuclear power plant |
Non-Patent Citations (1)
| Title |
|---|
| 李光伟，李宏艳: "氦质谱检漏技术在蒸发器制造与停堆期间的应用", 《科技创新与应用》 * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107289436A (en) * | 2016-03-31 | 2017-10-24 | 华北电力大学 | It is a kind of that there is the support flow-guiding structure for improving steam generator heat exchange efficiency |
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