CN205038971U - Long -term residual heat removal system of nuclear power station secondary side - Google Patents
Long -term residual heat removal system of nuclear power station secondary side Download PDFInfo
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- CN205038971U CN205038971U CN201520669506.1U CN201520669506U CN205038971U CN 205038971 U CN205038971 U CN 205038971U CN 201520669506 U CN201520669506 U CN 201520669506U CN 205038971 U CN205038971 U CN 205038971U
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The utility model provides a long -term residual heat removal system of nuclear power station secondary side, including steam generator, steam release pipeline is connected through main steam line through steam relief valve to the steam generator export, steam generator's income antilinear water supplying stop valve, water supply isolating valve are connected to the water -supply line, main steam line with parallel connection has emergent moisturizing case, heat exchanger between the water -supply line, the import of emergent moisturizing case is connected to main steam line through emergent moisturizing case import isolating valve with emergent supply water pipeline, emergent moisturizing case export is connected to the water -supply line through anxious moisturizing case export isolating valve, emergent moisturizing case outlet non -return valve, the heat exchanger import is arrived through heat exchanger import isolating valve, refrigeration cycle pipeline connection main steam line, the heat exchanger export is connected to the water -supply line through heat exchanger export isolating valve, heat exchanger outlet non -return valve.
Description
Technical field
The utility model relates to nuclear power station safety full guard field, relates to a kind of nuclear power station secondary side Residual heat removal system particularly.
Background technology
The emergency feedwater supply system of conventional pressurized water heap is as back-up system use when main feedwater was lost efficacy of main feed system.Under the breakdown operating mode of power station, emergency feedwater supply system is used for maintaining power station hot shutdown operating mode with time enough, and reactor is cooled to the state that residual heat removal system can put into operation.Emergency feedwater supply system belongs to engineered safeguards features, and under the transient state losing main feedwater or secondary side steam line break, emergency feedwater supply system is used to prevent reactor core from damaging, and discharges reactor core decay heat, until residual heat removal system puts into operation.Non-security relevant startup water supply system is provided with in third generation advanced pressurized water reactor, this system layout is at conventional island, in the main feedwater of forfeiture and forfeiture normal communication electricity event, feedwater is provided to steam generator from the water suction of condensate water tank, thus realize the depth defense function of discharging reactor coolant loop heat, prevent passive safety system action.In above process, the heat of reactor coolant loop passes to secondary coolant circuit system by steam generator, and secondary coolant circuit system is by taking heat out of to turbine bypass system or airborne release.
In existing presurized water reactor emergency feedwater supply system, mainly through power supply or diesel engine as drive source, and with rotating machinery to steam generator conveying feedwater, to take away reactor core decay heat.If can design a kind of have non-can dynamic characteristic and do not have the residual heat removal system of moving component, by making, the safety system of nuclear power station is more safe and reliable.
Utility model content
The purpose of this utility model is the long-term residual heat removal system providing a kind of nuclear power station secondary side, and do not need power drives and the Diesel Driven of traditional core power plant, and do not have rotating machinery and moving component, system is simple and reliable.
The long-term residual heat removal system of a kind of nuclear power station secondary side that the utility model provides, comprise steam generator, described steam generator outlet connects steam discharge line by main steam pipe through steam release valve, the entrance of described steam generator is through feed water check valve, feedwater isolation valve is connected to water-supply line, emergence compensating water case is connected in parallel between described main steam pipe and described water-supply line, heat exchanger, the import of described emergence compensating water case is connected to main steam pipe by emergence compensating water case import isolation valve and emergence compensating water pipeline, described emergence compensating water case outlet is through anxious water supply tank outlet isolation valve, emergence compensating water case outlet non-return valve is connected to water-supply line, described heat exchanger inlets is by heat exchanger inlets isolation valve, cool cycles pipeline is connected to described main steam pipe, described heat exchanger outlet is by heat exchanger outlet isolation valve, heat exchanger outlet non-return valve is connected to water-supply line.
In one embodiment, described main steam pipe is also connected to main steam isolation valve.The subcooled water of initial press is housed in described emergence compensating water case.
Further, described system is at the Residual heat removal initial stage, and being injected by gravity by emergence compensating water case is steam generator moisturizing, and by steam discharge line to airborne release steam, to take away reactor core decay heat.
Further, described system, at long-term cooling stage, by Natural Circulation by heat delivery heat exchanger, and passes through pipe outer air convection heat transfer by delivered heat to air.
Native system can be the system that safety is relevant, also can perform the non-safety-related system of depth defense function.
Accompanying drawing explanation
Fig. 1 is the long-term residual heat removal system general flow chart of nuclear power station secondary side.
Reference numeral
1-steam generator 2-main steam pipe 3-main steam isolation valve 4-steam release valve
5-steam discharge line 6-emergence compensating water case import isolation valve 7-emergence compensating water pipeline
8-emergence compensating water case 9-emergence compensating water case outlet isolation valve 10-emergence compensating water case outlet non-return valve
11-heat exchanger inlets isolation valve 12-long-term cool cycles pipeline 13-heat exchanger
14-heat exchanger outlet isolation valve 15-heat exchanger outlet non-return valve 16-feed water check valve
17-feedwater isolation valve 18-water-supply line
Embodiment
For enabling above-mentioned purpose of the present utility model, feature and advantage become apparent more, are described in further detail the utility model below in conjunction with the drawings and specific embodiments.
The present embodiment is implemented premised on technical solutions of the utility model, give detailed embodiment and concrete operating process, but protection domain of the present utility model is not limited to following embodiment.
In order to understand the utility model more clearly, occur to lose main water supply accident for nuclear power station below, the long-term residual heat removal system of composition graphs 1 to secondary side of the present utility model is described further.As shown in Figure 1, a kind of nuclear power station secondary side residual heat removal system that the utility model provides, comprise steam generator 1, described steam generator 1 exports and connects steam discharge line 2 by main steam pipe through steam release valve, the entrance of described steam generator 1 is through feed water check valve 16, feedwater isolation valve 17 is connected to water-supply line 18, emergence compensating water case 8 is connected in parallel between described main steam pipe 2 and described water-supply line 18, heat exchanger 13, the import of described emergence compensating water case 8 is connected to main steam pipe 2 by emergence compensating water case 8 import isolation valve 6 and emergence compensating water pipeline 7, described emergence compensating water case outlet is through anxious water supply tank outlet isolation valve 9, emergence compensating water case 8 outlet non-return valve is connected to water-supply line 18, the import of described heat exchanger 13 is by heat exchanger inlets isolation valve 11, cool cycles pipeline 12 is connected to described main steam pipe 2, described heat exchanger outlet is by heat exchanger outlet isolation valve 14, heat exchanger outlet non-return valve 15 is connected to water-supply line 18.
The long-term residual heat removal system of secondary side is arranged on outside the containment of reactor, and under normal operation, the long-term residual heat removal system of secondary side is in stand-by state, is full of high pressure subcooled water in emergence compensating water case 8, is full of low pressure subcooled water in heat exchanger 13.By the import isolation valve 6,11 of emergence compensating water case 8 and heat exchanger 13 and outlet isolation valve 9,14 and non-return valve 10,15, itself and main steam pipe 2 and water-supply line 18 are isolated.
When occurring to lose main water supply accident, main steam isolation valve 3 and feedwater isolation valve 17 are closed, and steam release valve 4 is opened.Open emergence compensating water case import isolation valve 6 simultaneously, pressure in emergence compensating water case 8 and steam generator 1 secondary pressure in a basic balance time, open emergence compensating water case outlet isolation valve 9, the subcooled water in emergence compensating water case 8 injects steam generator 1 under gravity.Subcooled water is become saturated vapour by thermal conversion in steam generator 1, some vapor enters emergence compensating water case 8 and maintains pressure equilibrium, remaining steam enters air by steam release valve 4 and steam discharge line 5, thus realize taking away reactor core decay heat, until the normal residual heat removal system of primary Ioops puts into operation.
After the cooling that emergence compensating water case 8 completes the first stage, as long-term cooling need be realized by secondary side residual heat removal system, then open heat exchanger inlets isolation valve 11 and outlet isolation valve 14 successively, at steam generator 1, main steam pipe 2, form natural convection loop between cool cycles pipeline 12 and water-supply line 18 for a long time, heat, by heat being entered air by pipe outer convection heat transfer in heat exchanger 13, realizes long-term Residual heat removal.
Said process utilizes non-active equipment and discharge of steam, and convection heat transfer takes away decay heat and the sensible heat of primary Ioops, realizes the cooling of primary Ioops, has good feasibility and reliability.
The connection of former components is only exemplary illustration of the present utility model and non-limitative illustration, also can be other connected modes.
Although accompanying drawing describes example comprehensively, various diagram can illustrate exemplary architecture of the present disclosure or other configurations, and it is with helping understand the Characteristic and function that can comprise in the disclosure.The disclosure is not limited to the exemplary architecture that illustrates or configuration, but available various substituting framework and configuration are implemented.In addition, although describe the disclosure about various example and realization above, should be understood that various Characteristic and function of one or more description in the example shown are not limited to describe their specific examples in their applicability.But, one or more in other examples of the present disclosure, they can be employed individually or with certain combination, and no matter whether such example is described, and no matter such feature as the part of the example described by this place.Again, the scope of the present disclosure should not by any one restriction of above-mentioned example.
In this instructions, each embodiment adopts the mode of going forward one by one to describe, and what each embodiment stressed is the difference with other embodiments, between each embodiment identical similar portion mutually see.For system disclosed in embodiment, owing to corresponding to the method disclosed in Example, so description is fairly simple, relevant part illustrates see method part.
Those skilled in the art can use distinct methods to realize described function to each specifically should being used for, but this realization should not thought and exceeds scope of the present utility model.
Obviously, those skilled in the art can carry out various change and modification to utility model and not depart from spirit and scope of the present utility model.Like this, if these amendments of the present utility model and modification belong within the scope of the utility model claim and equivalent technologies thereof, then the utility model is also intended to comprise these change and modification.
Claims (6)
1. the long-term residual heat removal system of a nuclear power station secondary side, it is characterized in that, comprise steam generator, described steam generator outlet connects steam discharge line by main steam pipe through steam release valve, the entrance of described steam generator is through feed water check valve, feedwater isolation valve is connected to water-supply line, emergence compensating water case is connected in parallel between described main steam pipe and described water-supply line, heat exchanger, the import of described emergence compensating water case is connected to main steam pipe by emergence compensating water case import isolation valve and emergence compensating water pipeline, described emergence compensating water case outlet is through anxious water supply tank outlet isolation valve, emergence compensating water case outlet non-return valve is connected to water-supply line, described heat exchanger inlets is by heat exchanger inlets isolation valve, cool cycles pipeline is connected to described main steam pipe, described heat exchanger outlet is by heat exchanger outlet isolation valve, heat exchanger outlet non-return valve is connected to water-supply line.
2. the long-term residual heat removal system of nuclear power station secondary side as claimed in claim 1, it is characterized in that, described main steam pipe is also connected to main steam isolation valve.
3. the long-term residual heat removal system of nuclear power station secondary side as claimed in claim 1, it is characterized in that, described emergence compensating water case is equipped with the subcooled water of initial press.
4. the long-term residual heat removal system of nuclear power station secondary side as claimed in claim 1, it is characterized in that, described system is at the Residual heat removal initial stage, and being injected by gravity by emergence compensating water case is steam generator moisturizing, and by steam discharge line to airborne release steam, to take away reactor core decay heat.
5. the long-term residual heat removal system of nuclear power station secondary side as claimed in claim 1, is characterized in that, described system at long-term cooling stage, by Natural Circulation by heat delivery heat exchanger, and by pipe outer air convection heat transfer by delivered heat to air.
6. the long-term residual heat removal system of nuclear power station secondary side as claimed in claim 1, is characterized in that, described system can be the system that safety is relevant, also can perform the non-safety-related system of depth defense function.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520669506.1U CN205038971U (en) | 2015-08-31 | 2015-08-31 | Long -term residual heat removal system of nuclear power station secondary side |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520669506.1U CN205038971U (en) | 2015-08-31 | 2015-08-31 | Long -term residual heat removal system of nuclear power station secondary side |
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| Publication Number | Publication Date |
|---|---|
| CN205038971U true CN205038971U (en) | 2016-02-17 |
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| CN201520669506.1U Expired - Fee Related CN205038971U (en) | 2015-08-31 | 2015-08-31 | Long -term residual heat removal system of nuclear power station secondary side |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105070327A (en) * | 2015-08-31 | 2015-11-18 | 上海核工程研究设计院 | Nuclear power station secondary side long-term waste heat removal system |
| CN107068214A (en) * | 2017-05-09 | 2017-08-18 | 中广核研究院有限公司 | Nuclear power plant steam air tapping equipment and secondary circuit pressure method for releasing |
-
2015
- 2015-08-31 CN CN201520669506.1U patent/CN205038971U/en not_active Expired - Fee Related
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105070327A (en) * | 2015-08-31 | 2015-11-18 | 上海核工程研究设计院 | Nuclear power station secondary side long-term waste heat removal system |
| CN107068214A (en) * | 2017-05-09 | 2017-08-18 | 中广核研究院有限公司 | Nuclear power plant steam air tapping equipment and secondary circuit pressure method for releasing |
| CN107068214B (en) * | 2017-05-09 | 2024-03-26 | 中广核研究院有限公司 | Nuclear power plant steam atmosphere discharge device and two-loop pressure release method |
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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: 20160217 Termination date: 20160831 |