CN202813324U - Heat pipe type vapor generator for nuclear power unit - Google Patents
Heat pipe type vapor generator for nuclear power unit Download PDFInfo
- Publication number
- CN202813324U CN202813324U CN201220432621.3U CN201220432621U CN202813324U CN 202813324 U CN202813324 U CN 202813324U CN 201220432621 U CN201220432621 U CN 201220432621U CN 202813324 U CN202813324 U CN 202813324U
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- secondary side
- housing
- heat pipe
- power unit
- nuclear power
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Abstract
The utility model discloses a heat pipe type vapor generator for a nuclear power unit, and belongs to the field of nuclear engineering. The heat pipe type vapor generator for the nuclear power unit comprise a tubular shell body and is characterized in that a tube plate is fixed inside the shell body in a seal mode, and the tube plate divides the shell body into a lower space and an upper space. A heat pipe bundle component penetrating through the lower space and the upper space is fixed on the tube plate. The bottom portion of the shell body is sealed, and a first return channel refrigerant inlet and a first return channel refrigerant outlet are formed in the side wall of the shell body of the lower space, and are used for the passing in and passing out of first return channel refrigerant. A secondary side water supply inlet is formed in the side wall of the upper portion of the shell body of the upper space, a secondary side barrel body is arranged inside the upper space, the secondary side barrel body covers a part of the heat pipe bundle component inside the upper space, a gap is arranged between the secondary side barrel body and the tube plate, and the top end of the secondary side barrel body is sequentially connected with a steam separator and a steam drying device. Compared with the prior art, the heat pipe type vapor generator for the nuclear power unit achieves the physical isolation of the first return channel refrigerant and second return channel refrigerant, and strengthens the safety and the economy of the nuclear power unit.
Description
Technical field
The utility model belongs to the nuclear engineering field, relates to particularly a kind of nuclear power unit heat pipe evaporator.
Background technology
Extensively adopt at present U-shaped pipe type steam generator in the nuclear power unit, its operation principle is: temperature is higher and have highly radioactive reactor-loop cooling agent and flow in U-shaped pipe, heat the outer secondary circuit feedwater of U-shaped pipe, make feedwater become steam, for the acting of secondary circuit steam turbine; One circuit cools agent is back to reactor after by evaporator cools, reenters the evaporimeter heat release through the reactor heating.Because U-shaped pipe quantity is many, tube wall is thin, work under bad environment, and the situation of U-shaped pipe corrosion failure occurs often, causes radioactive substance to leak to the secondary circuit side, produce the nuclear safety problem.And in case U-shaped tracheal rupture and find that radioactive substance leaks just needs nuclear power unit to shut down and carries out the evaporimeter plugging, and then affected the normal operation of unit, improved operating cost, reduced the economy of nuclear power unit.
The utility model content
Technical problem to be solved in the utility model just provides a kind of nuclear power unit heat pipe evaporator, can realize the physical isolation of a circuit cools agent and secondary circuit feedwater, strengthens security and the economy of nuclear power unit.
For solving the problems of the technologies described above, a kind of nuclear power unit heat pipe evaporator that the utility model provides, the housing that comprises tubular, its special feature is: sealing is fixed with tube sheet in the described housing, and tube sheet is separated into lower space and upper space with housing; Be fixed with the heating pipe tread assembly that runs through described lower space and upper space on the tube sheet; The sealed bottom of described housing has a circuit cools agent entrance and circuit cools agent outlet on the housing sidewall of lower space, be used for the discrepancy of a circuit cools agent; The housing upper portion side wall of upper space has the secondary side feed-water inlet, be provided with the secondary side cylindrical shell in the upper space, the secondary side cylindrical shell covers described heating pipe tread assembly and also and between tube sheet is provided with the interval in the part of upper space, and the top of secondary side cylindrical shell connects steam-water separator and vapor drying plant successively.
Further, a described circuit cools agent entrance is positioned at the housing sidewall upper end of lower space, and circuit cools agent outlet is positioned at the housing sidewall lower end of lower space; The housing sidewall of lower space is provided with some deflection plates, is used for turning to of a circuit cools agent and fixing of heating pipe tread assembly.
Further, be provided with some grid spacers in the described secondary side cylindrical shell, be used for the fixing of heating pipe tread assembly.
Compared with prior art, the beneficial effects of the utility model are: by the heating pipe tread assembly is installed on the tube sheet, realized the physical isolation of a circuit cools agent and secondary circuit feedwater, avoided both directly to contact, primary side or the secondary side of heat pipe break, all can not cause a highly radioactive circuit cools agent to leak to secondary circuit, steam generator still can continue operation, also namely this structure is that radioactive substance has increased safety curtain one, and then has improved security and the economy of nuclear power unit.
Description of drawings
Fig. 1 is the structural representation of an embodiment of the utility model.
Among the figure: 1-housing, 2-tube sheet, 3-end socket, 4-one circuit cools agent entrance, 5-one circuit cools agent outlet, 6-deflection plate, 7-secondary side cylindrical shell, 8-heating pipe tread assembly, 9-secondary side feed-water inlet, 10-steam-water separator, 11-vapor drying plant, 12-secondary side steam (vapor) outlet, 13-grid spacer.
The specific embodiment
Below in conjunction with accompanying drawing specific embodiment of the utility model is described in further detail.
As shown in Figure 1, a kind of nuclear power unit heat pipe evaporator of the present utility model comprises housing 1 and the heating pipe tread assembly 8 of tubular, and housing 1 interior sealing is fixed with tube sheet 2, and tube sheet 2 is separated into lower space and upper space with housing 1.Heating pipe tread assembly 8 is fixed on the tube sheet 2 by modes such as expand tube and welding, and this heating pipe tread assembly 8 has run through lower space and the upper space of housing 1.The bottom of housing 1 is provided with end socket 3, makes lower space and extraneous sealing.Housing 1 sidewall upper of lower space has a circuit cools agent entrance 4, the lower end has circuit cools agent outlet 5; In addition, housing 1 sidewall of lower space also is provided with some deflection plates 6, is used for turning to of a circuit cools agent, and makes heating pipe tread assembly 8 fixing with housing 1.Housing 1 upper portion side wall of upper space has secondary side feed-water inlet 9, in upper space, be provided with secondary side cylindrical shell 7, secondary side cylindrical shell 7 cover above-mentioned heating pipe tread assembly 8 the part of upper space and and 2 of tube sheets be provided with the interval, be convenient to entering of water, in secondary side cylindrical shell 7, also be provided with some grid spacers 13, be used for the fixing of heating pipe tread assembly 8, prevent tube bundle vibration.The top of secondary side cylindrical shell 7 connects steam-water separator 10 and vapor drying plant 11 successively, and the top of vapor drying plant 11 and housing 1 is secondary side steam (vapor) outlet 12.
Operation principle of the present utility model is: in the lower space of housing 1, one circuit cools agent enters through a circuit cools agent entrance 4, turn to through deflection plate 6, finally flow out from circuit cools agent outlet 5, during opposite heat tube tube bundle assembly 8 heat in the part of lower space; In the upper space of housing 1, feedwater enters from secondary circuit feed-water intake 9, decline passway along secondary side cylindrical shell 7 and housing 1 formation enters in the secondary side cylindrical shell 7, feedwater through heating pipe tread assembly 8 after the heating of the part of upper space, form steam water interface, arrive secondary side cylindrical shell 7 tops, successively after steam-water separator 10 and vapor drying plant 11 improve steam qualitys, steam is through secondary side steam (vapor) outlet 12 output housings 1 again.
Core of the present utility model is to be provided with tube sheet 2 physical isolation has been carried out in a circuit cools agent and secondary circuit feedwater, and heat with the heat pipe that runs through the two region, for radioactive substance has increased safety curtain one, reduce the shutdown accident that heat exchange pipe of evaporator breaks and causes, improved security and the economy of nuclear power unit.So its protection domain is not limited to above-described embodiment.Obviously, those skilled in the art can carry out various changes and distortion to the utility model and not break away from scope and spirit of the present utility model, for example: it is described that the setting position of a circuit cools agent entrance 4, circuit cools agent outlet 5 is not limited to embodiment, if be convenient to cooling agent discrepancy and with the sufficient heat exchange of heat pipe; The structural parameters such as the number of deflection plate 6 and interval also can be adjusted according to housing 1 specification etc.; Whether grid spacer 13 arranges, its concrete structure also can be determined according to actual needs etc.If these changes and distortion belong in the scope of the utility model claim and equivalent technologies thereof, then the utility model also is intended to comprise these changes and is out of shape interior.
Claims (3)
1. nuclear power unit heat pipe evaporator comprises the housing (1) of tubular, and it is characterized in that: sealing is fixed with tube sheet (2) in the described housing (1), and tube sheet (2) is separated into lower space and upper space with housing (1); Be fixed with the heating pipe tread assembly (8) that runs through described lower space and upper space on the tube sheet (2); The sealed bottom of described housing (1) has a circuit cools agent entrance (4) and circuit cools agent outlet (5) on the housing of lower space (1) sidewall, be used for the discrepancy of a circuit cools agent; The housing of upper space (1) upper portion side wall has secondary side feed-water inlet (9), be provided with secondary side cylindrical shell (7) in the upper space, secondary side cylindrical shell (7) cover described heating pipe tread assembly (8) the part of upper space and and tube sheet (2) between be provided with the interval, the top of secondary side cylindrical shell (7) connects steam-water separator (10) and vapor drying plant (11) successively.
2. a kind of nuclear power unit heat pipe evaporator according to claim 1, it is characterized in that: a described circuit cools agent entrance (4) is positioned at housing (1) sidewall upper of lower space, and circuit cools agent outlet (5) is positioned at housing (1) side wall lower ends of lower space; The housing of lower space (1) sidewall is provided with some deflection plates (6), is used for turning to of a circuit cools agent and fixing of heating pipe tread assembly (8).
3. a kind of nuclear power unit heat pipe evaporator according to claim 1 and 2 is characterized in that: be provided with some grid spacers (13) in the described secondary side cylindrical shell (7), be used for the fixing of heating pipe tread assembly (8).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201220432621.3U CN202813324U (en) | 2012-08-29 | 2012-08-29 | Heat pipe type vapor generator for nuclear power unit |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201220432621.3U CN202813324U (en) | 2012-08-29 | 2012-08-29 | Heat pipe type vapor generator for nuclear power unit |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN202813324U true CN202813324U (en) | 2013-03-20 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201220432621.3U Expired - Lifetime CN202813324U (en) | 2012-08-29 | 2012-08-29 | Heat pipe type vapor generator for nuclear power unit |
Country Status (1)
| Country | Link |
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| CN (1) | CN202813324U (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103425845A (en) * | 2013-08-26 | 2013-12-04 | 中国科学院合肥物质科学研究院 | Safe reliability evaluating system and method for nuclear power device |
| CN103471810A (en) * | 2013-09-16 | 2013-12-25 | 哈尔滨工程大学 | Interbank two-phase flow instability and alternating heat stress research testing device under load shedding disturbance |
| CN106124076A (en) * | 2016-07-06 | 2016-11-16 | 中国核动力研究设计院 | Steam generator heat-transfer pipe refluence monitoring device |
-
2012
- 2012-08-29 CN CN201220432621.3U patent/CN202813324U/en not_active Expired - Lifetime
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103425845A (en) * | 2013-08-26 | 2013-12-04 | 中国科学院合肥物质科学研究院 | Safe reliability evaluating system and method for nuclear power device |
| CN103425845B (en) * | 2013-08-26 | 2016-07-06 | 中国科学院合肥物质科学研究院 | A kind of security reliability for nuclear power unit evaluates system and method |
| CN103471810A (en) * | 2013-09-16 | 2013-12-25 | 哈尔滨工程大学 | Interbank two-phase flow instability and alternating heat stress research testing device under load shedding disturbance |
| CN103471810B (en) * | 2013-09-16 | 2015-12-02 | 哈尔滨工程大学 | Interbank two-phase flow instability and alternating thermal stress development test device under removal of load disturbance |
| CN106124076A (en) * | 2016-07-06 | 2016-11-16 | 中国核动力研究设计院 | Steam generator heat-transfer pipe refluence monitoring device |
| CN106124076B (en) * | 2016-07-06 | 2017-03-08 | 中国核动力研究设计院 | Steam generator heat-transfer pipe flows backwards monitoring device |
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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 |
Granted publication date: 20130320 |
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| CX01 | Expiry of patent term |