CN202522504U - Experiment system simulating material corrosion of primary circuit of nuclear power plant - Google Patents
Experiment system simulating material corrosion of primary circuit of nuclear power plant Download PDFInfo
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- CN202522504U CN202522504U CN2012201036789U CN201220103678U CN202522504U CN 202522504 U CN202522504 U CN 202522504U CN 2012201036789 U CN2012201036789 U CN 2012201036789U CN 201220103678 U CN201220103678 U CN 201220103678U CN 202522504 U CN202522504 U CN 202522504U
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Abstract
The utility model discloses an experiment system simulating the material corrosion of a primary circuit of a nuclear power plant. A water supply device comprises a primary circuit water supply box; the primary circuit water supply box is connected with a water storage box through a water supply box water inlet electric valve, and feeds water into a first-level buffer tank through a high-pressure water supply pump; an argon storage tank is arranged at one end of the first-level buffer tank; the other end of the first-level buffer tank is connected with an experiment device; the experiment device comprises a corrosion simulation experiment platform, and a circulation pump and a first electric heating pipe which are arranged in the experiment device circuit; the experiment platform is also connected in parallel with a bypass electric valve; a pressure adjusting valve is also arranged in the experiment device circuit; a second electric heating pipe is arranged between the first-level buffer tank and the argon storage tank; the first-level buffer tank is connected with a pollution discharge pool through a drainage electromagnetic valve; and the experiment device realizes the medium parameters required by the inlet of an experiment section mainly by increasing pressure of the water at the inlet through the circulation water pump and heating the water through the first electric heating pipe so as to meet the experiment requirements.
Description
Technical field
The utility model relates to simulation nuclear power station experimental system, is specifically related to a kind of simulation nuclear power station one return path materials corrosion experiment 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 a kind of simulation nuclear power station one return path materials corrosion experiment 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 system; Simple in structure, simple to operate.
To achieve these goals, the technical scheme of the utility model is:
A kind of simulation nuclear power station one return path materials corrosion experiment system comprises waterworks and experimental provision,
Said waterworks comprise a loop feed-tank; One loop feed-tank is connected with reserve tank through feed-tank water inlet motorized valve; A said loop feed-tank is sent water into the first-level buffer jar through high pressure water pump; Said first-level buffer jar one end is provided with argon storage tank, and the first-level buffer jar other end is connected with experimental provision
Said experimental provision comprises simulation corrosion experiment platform and is arranged at the ebullator and first electric heating tube in the experimental provision loop.
Said experiment porch also parallel connection is provided with the bypass motorized valve.
Said experimental provision also is provided with pressure-regulating valve in the loop.
Be provided with second electric heating tube between said first-level buffer jar and the argon storage tank.
Said first-level buffer jar is connected with the blowdown pond through the solenoid valve that discharges water.
Experimental system mainly is earlier to boost the water of experimental provision import through water circulating pump, heats up through first electric heating tube, thereby reaches the medium parameter of experimental section import requirement, satisfies requirement of experiment.
The positive progressive effect of the utility model is: can obtain the influence to material FAC behavior of different tube diameters and shape pipe, different temperatures, different in flow rate, different dissolved oxygen, different pH, different quality correctives through this experimental system.
Description of drawings
Fig. 1 is the fundamental diagram of the utility model.
Embodiment
Below in conjunction with accompanying drawing, to specify the technical scheme of the utility model.
A kind of simulation nuclear power station one return path materials corrosion experiment system comprises waterworks and experimental provision,
Said waterworks comprise a loop feed-tank 1; One loop feed-tank is connected with reserve tank 3 through feed-tank water inlet motorized valve 2; A said loop feed-tank 1 is sent water into first-level buffer jar 5 through high pressure water pump 4; Said first-level buffer jar 5 one ends are provided with argon storage tank 6, and first-level buffer jar 5 other ends are connected with experimental provision
Said experimental provision comprises simulation corrosion experiment platform 7 and is arranged at the ebullator 8 and first electric heating tube 9 in the experimental provision loop.
Said experiment porch also parallel connection is provided with bypass motorized valve 10.
Said experimental provision also is provided with pressure-regulating valve 11 in the loop.
Be provided with second electric heating tube 12 between said first-level buffer jar and the argon storage tank.
Said first-level buffer jar is connected with blowdown pond 14 through the solenoid valve 13 that discharges water.
Recirculated water via water circulating pump before behind the water purifier filtration by the water circulating pump pressurization, after deliver to first electric heating tube and be heated, get into the experiment pipeline section then, wash away the experiment pipeline section after, behind throttling orifice plate, get back to the water circulating pump inlet, back and forth experiment circulation.
The first-level buffer jar is that the water yield and the argon gas that are used for keeping circulation line are kept in balance, and high pressure water pump is to be used for moisturizing in experimental system regularly.
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 (5)
1. simulation nuclear power station one a return path materials corrosion experiment system comprises waterworks and experimental provision, it is characterized in that; Said waterworks comprise a loop feed-tank; One loop feed-tank is connected with reserve tank through feed-tank water inlet motorized valve, and a said loop feed-tank is sent water into the first-level buffer jar through high pressure water pump, and said first-level buffer jar one end is provided with argon storage tank; The first-level buffer jar other end is connected with experimental provision
Said experimental provision comprises simulation corrosion experiment platform and is arranged at the ebullator and first electric heating tube in the experimental provision loop.
2. a kind of simulation nuclear power station according to claim 1 one return path materials corrosion experiment system is characterized in that said experiment porch also parallel connection is provided with the bypass motorized valve.
3. a kind of simulation nuclear power station according to claim 1 one return path materials corrosion experiment system is characterized in that said experimental provision also is provided with pressure-regulating valve in the loop.
4. a kind of simulation nuclear power station according to claim 1 one return path materials corrosion experiment system is characterized in that, is provided with second electric heating tube between said first-level buffer jar and the argon storage tank.
5. a kind of simulation nuclear power station according to claim 1 one return path materials corrosion experiment system is characterized in that said first-level buffer jar is connected with the blowdown pond through the solenoid valve that discharges water.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012201036789U CN202522504U (en) | 2012-03-19 | 2012-03-19 | Experiment system simulating material corrosion of primary circuit of nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012201036789U CN202522504U (en) | 2012-03-19 | 2012-03-19 | Experiment system simulating material corrosion of primary circuit of nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN202522504U true CN202522504U (en) | 2012-11-07 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
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| CN2012201036789U Expired - Fee Related CN202522504U (en) | 2012-03-19 | 2012-03-19 | Experiment system simulating material corrosion of primary circuit of nuclear power plant |
Country Status (1)
| Country | Link |
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| CN (1) | CN202522504U (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103474110A (en) * | 2013-08-26 | 2013-12-25 | 上海交通大学 | Test loop device of high-temperature and high-pressure nuclear reactor |
| CN104409118A (en) * | 2014-10-23 | 2015-03-11 | 华北电力大学 | Thermal hydraulic experimental system and method for study on corrosion product deposit of fusion reactor |
| 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 |
| CN111486101A (en) * | 2020-04-26 | 2020-08-04 | 上海交通大学 | Pressure adjusting system of nuclear main pump experiment table |
-
2012
- 2012-03-19 CN CN2012201036789U patent/CN202522504U/en not_active Expired - Fee Related
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103474110A (en) * | 2013-08-26 | 2013-12-25 | 上海交通大学 | Test loop device of high-temperature and high-pressure nuclear reactor |
| CN103474110B (en) * | 2013-08-26 | 2016-03-02 | 上海交通大学 | High Temperature High Pressure nuclear reactor test loop device |
| CN104409118A (en) * | 2014-10-23 | 2015-03-11 | 华北电力大学 | Thermal hydraulic experimental system and method for study on corrosion product deposit of fusion reactor |
| 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 |
| CN111486101A (en) * | 2020-04-26 | 2020-08-04 | 上海交通大学 | Pressure adjusting system of nuclear main pump experiment table |
| CN111486101B (en) * | 2020-04-26 | 2021-08-06 | 上海交通大学 | Pressure adjusting system of nuclear main pump experiment table |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20121107 Termination date: 20190319 |