CN202522505U - Experiment system for simulating two-loop pure liquid phase flowing acceleration corrosion of nuclear power station - Google Patents
Experiment system for simulating two-loop pure liquid phase flowing acceleration corrosion of nuclear power station Download PDFInfo
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- CN202522505U CN202522505U CN2012201036810U CN201220103681U CN202522505U CN 202522505 U CN202522505 U CN 202522505U CN 2012201036810 U CN2012201036810 U CN 2012201036810U CN 201220103681 U CN201220103681 U CN 201220103681U CN 202522505 U CN202522505 U CN 202522505U
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Abstract
The utility model relates to an experiment system for simulating two-loop pure liquid phase flowing acceleration corrosion of a nuclear power station. The experiment system comprises a water circulation system and a liquid phase simulation experiment system, wherein the water circulation system and the liquid phase simulation experiment system are connected through a liquid phase heat exchanger, the water circulation system comprises a two-loop water supply tank, the two-loop water supply tank is connected with the liquid change heat exchanger through a valve group capable of controlling the on-off state of a water path and is connected with a liquid phase cooler through the liquid change heat exchanger, the liquid phase cooler is connected with a capacity expansion container, the liquid phase simulation experiment system comprises a liquid phase experiment platform, the liquid phase experiment platform is parallelly provided with bypass electric valves, a liquid phase heater is also arranged in a loop of the liquid phase simulation experiment system, circulating water comes out from the two-loop water supply tank, is boosted by a circulating water pump after being filtered by a front water filter of the circulating water pump and then enters the liquid phase heat exchanger to realize the heat exchange with experimented high-temperature water, next, the circulating water is conveyed to the liquid phase heater to be heated and finally enters an experiment pipe section, the structure is simple, and the operation is simple.
Description
Technical field
The utility model relates to simulation nuclear power station experimental system, is specifically related to the pure liquid phase flow accelerated corrosion of a kind of simulation nuclear power station secondary circuit experimental system.
Background technology
Nuclear energy is as a kind of energy of efficient, economic, cleaning, solving energy crisis, improving and significant advantage is arranged aspect the environment, yet inscribing between the safety that the key factor that the restriction nuclear power develops rapidly is a nuclear power station.Because the Service Environment of light water reactor nuclear power station is a high-temperature high pressure water; And construction material all bears certain military service stress; So inevitably there is etching problem; Typical in corrosion fatigue, stress corrosion, erosion corrosion, crevice corrosion and spot corrosion or the like, to the very big potential threat of safe operation formation of nuclear power station.
Therefore study stainless steel corrosion resistance under the HTHP water environment, understand fully its environmental stress cracking mechanism, have important significance for theories and practical significance.
Summary of the invention
To the problems referred to above; The utility model relates to the pure liquid phase flow accelerated corrosion of a kind of simulation nuclear power station secondary circuit experimental system; Can obtain different tube diameters and shape pipe, different temperatures, different in flow rate, different dissolved oxygen, different pH, different quality correctives to the flow influence of accelerated corrosion behavior of material through this experimental provision; Simple in structure, simple to operate.
To achieve these goals, the technical scheme of the utility model is:
The pure liquid phase flow accelerated corrosion of a kind of simulation nuclear power station secondary circuit experimental system comprises water circulation system and liquid phase experimental system for simulating, and said water circulation system is connected through the liquid phase heat interchanger with the liquid phase experimental system for simulating,
Said water circulation system comprises the secondary circuit feed-tank; The secondary circuit feed-tank connects the liquid phase heat interchanger through the valve sets of may command water route break-make, and is connected with the liquid phase cools device through the liquid phase heat interchanger, and said liquid phase cools device is connected with flash vessel; Said valve sets mainly includes the stop valve that sets gradually; Pressure maintaining valve and non-return valve also are provided with ebullator in the said valve sets
Said liquid phase experimental system for simulating comprises the liquid phase experiment porch, and the parallel connection of liquid phase experiment porch is provided with the bypass motorized valve, also is provided with the liquid phase well heater in the loop of said liquid phase experimental system for simulating.
Said liquid phase heat interchanger lower end is connected with blowdown system.
The water delivering orifice of said flash vessel is connected with chemical water treatment system.
Said flash vessel and blowdown system are provided with the motorized valve that discharges water.
The positive progressive effect of the utility model is: can obtain different tube diameters and shape pipe, different temperatures, different in flow rate, different dissolved oxygen, different pH, different quality correctives to the flow influence of accelerated corrosion behavior of material through this experimental provision; Simple in structure, simple to operate.
Description of drawings
Fig. 1 is the experimental system figure of the utility model.
Embodiment
Below in conjunction with accompanying drawing, to specify the technical scheme of the utility model.
The pure liquid phase flow accelerated corrosion of a kind of simulation nuclear power station secondary circuit experimental system comprises water circulation system and liquid phase experimental system for simulating, and said water circulation system is connected through the liquid phase heat interchanger with the liquid phase experimental system for simulating,
Said water circulation system comprises secondary circuit feed-tank 1; Secondary circuit feed-tank 1 connects liquid phase heat interchanger 2 through the valve sets of may command water route break-make, and is connected with liquid phase cools device 3 through liquid phase heat interchanger 2, and said liquid phase cools device 3 is connected with flash vessel 4; Said valve sets mainly includes the stop valve that sets gradually; Pressure maintaining valve and non-return valve also are provided with ebullator in the said valve sets
Said liquid phase experimental system for simulating comprises liquid phase experiment porch 5, and 5 parallel connections of liquid phase experiment porch are provided with bypass motorized valve 6, also is provided with liquid phase well heater 7 in the loop of said liquid phase experimental system for simulating.
Said liquid phase heat interchanger lower end is connected with blowdown system 8.
The water delivering orifice of said flash vessel is connected with chemical water treatment system.
Said flash vessel and blowdown system are provided with the motorized valve that discharges water.
Recirculated water comes out from giving secondary circuit feed-tank 1, and via being boosted by water circulating pump behind the water purifier filtration before the water circulating pump, the high-temperature water heat exchange after getting into liquid phase heat interchanger 2 again and testing is delivered to liquid phase well heater 7 then and is heated, and gets into the experiment pipeline section at last.Wash away the high-temperature water of experiment behind the pipeline section, get into liquid phase heat interchanger 2 and water at low temperature heat exchange as the heating thermal source, then through the pressure-regulating valve decompression, get into 3 coolings of liquid phase cools device again, get into flash vessel 8 dilatations at last, the water after the dilatation gets into chemical water treatment system.Chilled water after treatment is driven into feed-tank again, the repeated experiments circulation, and wherein liquid phase well heater 7 is heating thermals source of whole circulation system.
More than show and described ultimate principle of the utility model and the advantage of principal character and the utility model.The technician of the industry should understand; The utility model is not restricted to the described embodiments; The principle of describing in the foregoing description and the instructions that the utility model just is described, under the prerequisite that does not break away from the utility model spirit and scope, the utility model also has various changes and modifications; These variations and improvement all fall in the utility model scope that requires protection, and the utility model requires protection domain to be defined by appending claims and equivalent thereof.
Claims (4)
1. the pure liquid phase flow accelerated corrosion of a simulation nuclear power station secondary circuit experimental system comprises water circulation system and liquid phase experimental system for simulating, it is characterized in that said water circulation system is connected through the liquid phase heat interchanger with the liquid phase experimental system for simulating,
Said water circulation system comprises the secondary circuit feed-tank; The secondary circuit feed-tank connects the liquid phase heat interchanger through the valve sets of may command water route break-make, and is connected with the liquid phase cools device through the liquid phase heat interchanger, and said liquid phase cools device is connected with flash vessel; Said valve sets mainly includes the stop valve that sets gradually; Pressure maintaining valve and non-return valve also are provided with ebullator in the said valve sets
Said liquid phase experimental system for simulating comprises the liquid phase experiment porch, and the parallel connection of liquid phase experiment porch is provided with the bypass motorized valve, also is provided with the liquid phase well heater in the loop of said liquid phase experimental system for simulating.
2. the pure liquid phase flow accelerated corrosion of a kind of simulation nuclear power station secondary circuit according to claim 1 experimental system is characterized in that said liquid phase heat interchanger lower end is connected with blowdown system.
3. the pure liquid phase flow accelerated corrosion of a kind of simulation nuclear power station secondary circuit according to claim 1 experimental system is characterized in that the water delivering orifice of said flash vessel is connected with chemical water treatment system.
4. the pure liquid phase flow accelerated corrosion of a kind of simulation nuclear power station secondary circuit according to claim 1 experimental system is characterized in that said flash vessel and blowdown system are provided with the motorized valve that discharges water.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012201036810U CN202522505U (en) | 2012-03-19 | 2012-03-19 | Experiment system for simulating two-loop pure liquid phase flowing acceleration corrosion of nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN2012201036810U CN202522505U (en) | 2012-03-19 | 2012-03-19 | Experiment system for simulating two-loop pure liquid phase flowing acceleration corrosion of nuclear power station |
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| CN202522505U true CN202522505U (en) | 2012-11-07 |
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| CN2012201036810U Expired - Fee Related CN202522505U (en) | 2012-03-19 | 2012-03-19 | Experiment system for simulating two-loop pure liquid phase flowing acceleration corrosion of nuclear power station |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106124393A (en) * | 2016-08-23 | 2016-11-16 | 上海交通大学 | Flowing accelerated corrosion assay device and using method thereof |
| CN109991157A (en) * | 2019-04-08 | 2019-07-09 | 中国核动力研究设计院 | A kind of high-temperature high pressure water corrosion product dissolution release device |
-
2012
- 2012-03-19 CN CN2012201036810U patent/CN202522505U/en not_active Expired - Fee Related
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106124393A (en) * | 2016-08-23 | 2016-11-16 | 上海交通大学 | Flowing accelerated corrosion assay device and using method thereof |
| CN109991157A (en) * | 2019-04-08 | 2019-07-09 | 中国核动力研究设计院 | A kind of high-temperature high pressure water corrosion product dissolution release device |
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Granted publication date: 20121107 Termination date: 20190319 |
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| CF01 | Termination of patent right due to non-payment of annual fee |