CN202887588U - Steam generator model of pressurized water reactor nuclear power plant - Google Patents
Steam generator model of pressurized water reactor nuclear power plant Download PDFInfo
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- CN202887588U CN202887588U CN 201220577645 CN201220577645U CN202887588U CN 202887588 U CN202887588 U CN 202887588U CN 201220577645 CN201220577645 CN 201220577645 CN 201220577645 U CN201220577645 U CN 201220577645U CN 202887588 U CN202887588 U CN 202887588U
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Abstract
The utility model discloses a steam generator model of a pressurized water reactor nuclear power plant. A steam outlet pipe nozzle is formed in the top of a model housing, a feedwater inlet is formed in the middle of the housing, a coolant inlet and a coolant outlet are formed in the bottom of the housing, an arc-shaped showing window is formed in a lower end socket at the bottom of the housing, the housing is integrally sectioned by 1/3; a steam dryer with a rectangular showing window, a plurality of cyclone blade type steam-water separators, a transparent feedwater ring pipe with a green light device, a transparent heat transfer pipe bundle with a red light device and a baffle plate are sequentially arranged in the housing from top to bottom, wherein one cyclone blade type steam-water separator is sectioned in the middle; and the green light device and the red light device are connected with a power supply through a control switch in front of an exhibition stand. The model structure is simplified on the basis of the main structure of the steam generator and the flow, by combining with the light process, and thus audiences can clearly and visually know the work principle, flow and main structure of the steam generator model.
Description
Technical field
The utility model relates to a kind of steam generator principle of work of PWR nuclear power plant and model of primary structure thereof showed.
Background technology
Steam generator is the heat energy that reactor coolant obtains from reactor core to be passed to secondary circuit working medium make it become the heat-exchange apparatus of steam.That the steam generator of PWR nuclear power plant adopts is vertical, Natural Circulation, U type pipe type steam generator, the cooling medium that flows out from reactor is approached by the import of the low head of steam generator through a loop heat pipe section and enters hydroecium, then in the type of falling U tube bank, flow, the outside surface of the type of falling U pipe contacts with the secondary circuit feedwater, heat transfer is to secondary circuit water, and make its vaporization, finish one, the heat interchange between secondary circuit.After the heat that one circuit cools agent is carried was passed to secondary circuit, temperature reduced, and passed through outlet hydroecium and the discharge connection of low head again, and then the transition conduit that flows to a loop enters the suction inlet of main pump.
The feedwater of secondary circuit enters the feedwater endless tube by the water supply connecting tube of steam generator, enter lower shell and the annulus (be decline passway) of tube bank between the sleeve by one group of reversed J shape pipe on the endless tube, with flow downward after the isolated water of steam-water separator mixes, until bottom tube sheet, then turn to, (being rising passway) upwards flows outside the pipe of the type of falling U tube bank, the circuit cools agent heating of being flowed in the heat-transfer pipe, and a part of water flashes to steam.Steam water interface leaves inverted U tube bank top to be continued to rise, enter successively Spiralism type steam-water separator and exsiccator, after carbonated drink was separated, steam flowed to the steam turbine acting from the top exit of steam generator, and the water of separating then down mixes with feedwater and carries out recycle.
Its principle of work and flow process more complicated are abstract, lack intuitively teaching means, are difficult to allow the people understand in Popular Science Education.How simplifying literary writing by leaving out superfluous words on the basis of reaction primary structure and flow process, allow spectators understand its principle of work and primary structure thereof clear and intuitively, is the problem that scientific and technological modelling will be faced.
Summary of the invention
In order to solve above-mentioned drawback, technical problem to be solved in the utility model is, a kind of steam generator principle of work of PWR nuclear power plant and scientific and technological model of primary structure thereof showed is provided, and makes the learner can understand intuitively corresponding knowledge.In order to solve the problems of the technologies described above, the technical solution adopted in the utility model is the model steam generator of PWR nuclear power plant, it is characterized in that, described model cover top portion arranges the steam (vapor) outlet ozzle, and the shell middle part arranges feed-water intake, and outer casing bottom arranges coolant entrance and coolant outlet; The low head of outer casing bottom is offered the arc impression window, and shell integral body is done 1/3 and dissectd; Following mechanism sequentially is set in the shell from top to bottom: offer the steam dryer of rectangle impression window, several Spiralism type steam-water separators are provided with the transparent feedwater endless tube of green device, are provided with the transparent heat-transfer pipe tube bank of red light device, dividing plate; The middle part of one of them Spiralism type steam-water separator is dissectd; The green device is connected the front, exhibition booth with the red light device gauge tap connects power supply.
The beneficial effects of the utility model are that model structure is arranged on the basis of reflecting steam generator primary structure and flow process and simplifies literary writing by leaving out superfluous words, and in conjunction with the light flow process, can allow spectators understand its principle of work, flow process and primary structure thereof clear and intuitively.
Below in conjunction with the drawings and specific embodiments the utility model is described further.
Description of drawings
Accompanying drawing is the utility model structural representation.
Embodiment
Referring to accompanying drawing, reflect a kind of concrete structure of the present utility model, shell 1 top of the model steam generator of described PWR nuclear power plant arranges steam (vapor) outlet ozzle 2, and shell 1 middle part arranges feed-water intake 3, and shell 1 bottom arranges coolant entrance 4 and coolant outlet 5; The low head 6 of shell 1 bottom is offered arc impression window 7, and shell 1 integral body is done 1/3 and dissectd; Following mechanism sequentially is set from top to bottom: the steam dryer 9 of offering rectangle impression window 8 in the shell 1, several Spiralism type steam-water separators 10, be provided with the transparent feedwater endless tube 11 of green device, be provided with the transparent heat-transfer pipe tube bank 12 of red light device, dividing plate 13; The middle part of one of them Spiralism type steam-water separator 10 is dissectd; The green device is connected 14 fronts, exhibition booth with the red light device gauge tap connects power supply.
The gauge tap of closing, green device and red light device change the running orbit that shows cooling medium and steam by the light light and shade.
Claims (1)
1. the model steam generator of PWR nuclear power plant is characterized in that, described model cover top portion arranges the steam (vapor) outlet ozzle, and the shell middle part arranges feed-water intake, and outer casing bottom arranges coolant entrance and coolant outlet; The low head of outer casing bottom is offered the arc impression window, and shell integral body is done 1/3 and dissectd; Following mechanism sequentially is set in the shell from top to bottom: offer the steam dryer of rectangle impression window, several Spiralism type steam-water separators are provided with the transparent feedwater endless tube of green device, are provided with the transparent heat-transfer pipe tube bank of red light device, dividing plate; The middle part of one of them Spiralism type steam-water separator is dissectd; The green device is connected the front, exhibition booth with the red light device gauge tap connects power supply.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201220577645 CN202887588U (en) | 2012-11-06 | 2012-11-06 | Steam generator model of pressurized water reactor nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201220577645 CN202887588U (en) | 2012-11-06 | 2012-11-06 | Steam generator model of pressurized water reactor nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN202887588U true CN202887588U (en) | 2013-04-17 |
Family
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN 201220577645 Expired - Lifetime CN202887588U (en) | 2012-11-06 | 2012-11-06 | Steam generator model of pressurized water reactor nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN202887588U (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104658404A (en) * | 2015-03-19 | 2015-05-27 | 中国核动力研究设计院 | Simulation device of steam generator heat transfer tube bundle |
| CN105023498A (en) * | 2015-06-17 | 2015-11-04 | 中科华核电技术研究院有限公司 | Steam generator test system |
| 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 |
| CN110578915A (en) * | 2019-09-11 | 2019-12-17 | 常州大学 | Steam generator with preheater and superheater |
-
2012
- 2012-11-06 CN CN 201220577645 patent/CN202887588U/en not_active Expired - Lifetime
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104658404A (en) * | 2015-03-19 | 2015-05-27 | 中国核动力研究设计院 | Simulation device of steam generator heat transfer tube bundle |
| CN104658404B (en) * | 2015-03-19 | 2018-03-30 | 中国核动力研究设计院 | A kind of steam generator heat-transfer pipe beam analogue means |
| CN105023498A (en) * | 2015-06-17 | 2015-11-04 | 中科华核电技术研究院有限公司 | Steam generator test system |
| 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 |
| CN110578915A (en) * | 2019-09-11 | 2019-12-17 | 常州大学 | Steam generator with preheater and superheater |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term | ||
| CX01 | Expiry of patent term |
Granted publication date: 20130417 |