CN202948739U - Integrated pressurized water reactor coolant system - Google Patents
Integrated pressurized water reactor coolant system Download PDFInfo
- Publication number
- CN202948739U CN202948739U CN2012205491858U CN201220549185U CN202948739U CN 202948739 U CN202948739 U CN 202948739U CN 2012205491858 U CN2012205491858 U CN 2012205491858U CN 201220549185 U CN201220549185 U CN 201220549185U CN 202948739 U CN202948739 U CN 202948739U
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- China
- Prior art keywords
- pressure vessel
- reactor coolant
- reactor
- coolant system
- voltage stabilizer
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- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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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 relates to a nuclear power technology, and specifically discloses an integrated pressurized water reactor coolant system. The system comprises a pressure container and a reactor coolant pump, a reactor core is arranged in the pressure container, the reactor coolant pump is uniformly arranged outside the pressure container; the system further comprises a direct current steam generator at the upper part of the pressure container, and a voltage stabilizer, wherein the top of the voltage stabilizer is provided with a shower nozzle, and the bottom thereof is provided with a heating element; a pipeline at the top of the voltage stabilizer is provided with two rows of spring safety valves. The device can be used for eliminating large LOCA accidents and improving the safety of the reactor; meanwhile, the integrated pressurized water reactor coolant system is in compact arrangement, the limitation on the size of the plant site is reduced, the modularized generation and installation of the device are realized, the construction period is shortened, and the economic benefit is improved. The nuclear power (heat) device has a good market prospect due to the advantages of safety and economy, and is environment-friendly when being constructed and used at populated areas.
Description
Technical field
The utility model belongs to nuclear power technology, is specifically related to a kind of presurized water reactor coolant system.
Background technology
At present both at home and abroad operation or nuclear power (heat) the device reaction reactor coolant system that builds again generally adopt decentralized to arrange, namely by trunk line, main pump, steam generator are connected with reactor, and the independent steam stable-pressure device that arranges is controlled the pressure of reactor coolant loop.Due to the existence of trunk line, not only increased nuclear island equipment layout required space, also increased large LOCA(nuclear power station cooling agent and lost) probability that occurs of accident.Although U.S.'s third generation AP1000 technology has been cancelled the trunk line between main pump and steam generator, reactor directly still adopts trunk line to be connected with steam generator.The setting of trunk line not only makes reactor coolant loop need more arrangement space, has more increased the probability that large-break LOCA occurs.
Summary of the invention
The purpose of this utility model is to provide a kind of Integrated PWR coolant system, and it has cancelled the heavy caliber trunk line, makes the LOCA accident probability be minimized.
Realize that the technical solution of the utility model is as follows:
A kind of Integrated PWR coolant system, it comprises the reactor coolant pump in pressure vessel and the pressure vessel outside, and described pressure vessel inside is provided with reactor core, and described reactor coolant pump evenly is arranged on the pressure vessel outside; Also comprise once through steam generator, it is positioned at pressure vessel top; Also comprise voltage stabilizer, its top is provided with shower nozzle, and the bottom is provided with heating element, on the pipeline at described voltage stabilizer top, two row spring safety valves is installed.
In above-mentioned Integrated PWR coolant system: lower end one side of described pressure vessel is provided with spray pipe, and atomizing pump is installed on pipeline.
In above-mentioned Integrated PWR coolant system: be provided with jet pipe on described spray pipe.
In above-mentioned Integrated PWR coolant system: described pressure vessel top is provided with heap top exhaust system.
In above-mentioned Integrated PWR coolant system: described heap top exhaust system comprises the valvular pipeline of two-way band, and the two-way pipeline is connected with water tank.
The obtained beneficial effect of the utility model is as follows: the integral reactor coolant system that cooling medium pump, once through steam generator and reactor is integrated has been cancelled trunk line, can eliminate large LOCA accident, the security that has improved reactor; Simultaneously integral reactor coolant system characteristics of compact layout not only, reduced the restriction to the factory site size, and modularization that more can implement device generates installs, and shortening production cycle is increased economic efficiency.The advantage of above security and economy makes nuclear power (heat) device have good market outlook, nuclear power (heat) device is used in the construction of dense population areas have good environment friendly.
Description of drawings
Fig. 1 is Integrated PWR coolant system schematic diagram of the present utility model;
In figure: 1. reactor core; 2. pressure vessel; 3. once through steam generator; 4. reactor coolant pump; 5. voltage stabilizer; 6. spring safety valve; 7. atomizing pump; 8. pile the top exhaust system; 9. electrical heating elements; 10. water tank; 11. shower nozzle; 12. jet pipe.
Embodiment
Below in conjunction with the drawings and specific embodiments, the utility model is described in detail.
As shown in Figure 1, reactor core 1 is positioned at pressure vessel 2 bottoms, and once through steam generator 3 is positioned at pressure vessel 2 tops, keeps certain difference in height with reactor core 1, in order to avoid once through steam generator 3 bottoms are subject to the irradiation of high neutron activity level.Reactor coolant pump 4 is positioned at pressure vessel 2 both sides, and it is evenly arranged in cold section reactor core active region upper area of cooling medium around reactor pressure vessel 2 outsides, and the main pump that is directly installed on reactor pressure vessel 2 is taken over.
Integral reactor adopts the steam voltage stabilizing, and voltage stabilizer 5 is connected with reactor by the fluctuation pipe, and voltage stabilizer 5 comprises that the bottom is equipped with heating element 9, and two row spring safety valves 6 are installed on top duct, and device for cleaning pipeline is crossed water tank 10 and supplied water.
In order to solve the technical matters of the demand that can't satisfy the voltage stabilizer spraying because the main pump lift is less, in the lower end of reactor pressure vessel 2 side, spray pipe is installed, atomizing pump 7 is installed on pipeline.And on this section spray pipe, valve being installed, the spray pipe epimere directly is connected with the interior shower nozzle 11 of voltage stabilizer 5.Jet pipe 12 also is installed on spray pipe.
For the frequent take-off of spring safety valve 6 that prevents voltage stabilizer, in pressure vessel 2 installation heap top, tops exhaust system 8, be used for the exhaust under reactor coolant loop superpressure and accident conditions.It comprises the valvular pipeline of two-way band, and the two-way pipeline is connected with water tank 10.
From top to bottom the flow through heat-transfer pipe primary side of once through steam generator 3 of reactor coolant.Secondary side feedwater enter every once through steam generator 3 to water manifold, after distributing to water manifold, from bottom to top flow through the heat-transfer pipe of once through steam generator, and therein the absorption reaction reactor coolant heat and produce superheated vapor.Superheated vapor upwards flows into steam header, and enters the secondary circuit main steam system through steam connection.
Obviously, those skilled in the art can carry out various changes and modification and not break away from spirit and scope of the present utility model the utility model.If these are revised and within modification belongs to the scope of the utility model claim and equivalent technologies thereof, the utility model also is intended to comprise these changes and modification interior.
Claims (5)
1. Integrated PWR coolant system, it comprises the reactor coolant pump (4) outside pressure vessel (2) and pressure vessel (2), described pressure vessel (2) inside is provided with reactor core (1), it is characterized in that: described reactor coolant pump (4) evenly is arranged on outside pressure vessel (2); Also comprise once through steam generator (3), it is positioned at pressure vessel (2) top; Also comprise voltage stabilizer (5), its top is provided with shower nozzle (11), and the bottom is provided with heating element (9), on the pipeline at described voltage stabilizer (5) top, two row spring safety valves (6) is installed.
2. Integrated PWR coolant system as claimed in claim 1, it is characterized in that: lower end one side of described pressure vessel (2) is provided with spray pipe, and atomizing pump (7) is installed on pipeline.
3. Integrated PWR coolant system as claimed in claim 2, it is characterized in that: described spray pipe is provided with jet pipe (12).
4. Integrated PWR coolant system as claimed in claim 1 is characterized in that: described pressure vessel (2) top is provided with heap top exhaust system (8).
5. Integrated PWR coolant system as claimed in claim 4, it is characterized in that: described heap top exhaust system (8) comprises the valvular pipeline of two-way band, the two-way pipeline is connected with water tank (10).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012205491858U CN202948739U (en) | 2012-10-25 | 2012-10-25 | Integrated pressurized water reactor coolant system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012205491858U CN202948739U (en) | 2012-10-25 | 2012-10-25 | Integrated pressurized water reactor coolant system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN202948739U true CN202948739U (en) | 2013-05-22 |
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ID=48424431
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2012205491858U Expired - Lifetime CN202948739U (en) | 2012-10-25 | 2012-10-25 | Integrated pressurized water reactor coolant system |
Country Status (1)
| Country | Link |
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| CN (1) | CN202948739U (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103390435A (en) * | 2013-07-30 | 2013-11-13 | 中广核工程有限公司 | Exhaust device and method for pressure vessel of nuclear power plant reactor coolant system |
| WO2014090142A1 (en) * | 2012-12-13 | 2014-06-19 | 中国核动力研究设计院 | Circuit accident exhaust system of pressurized water reactor nuclear power plant |
| CN105632571A (en) * | 2014-12-01 | 2016-06-01 | 上海核工程研究设计院 | Integrated reactor equipment |
| CN106887263A (en) * | 2015-12-15 | 2017-06-23 | 中国核动力研究设计院 | The secondary laterally opened Heat Discharging System of Chinese of once through steam generator |
| CN108346476A (en) * | 2018-03-30 | 2018-07-31 | 中广核研究院有限公司 | Reactor and divide pot type voltage-stablizer |
| CN108986933A (en) * | 2018-08-01 | 2018-12-11 | 中广核研究院有限公司 | Modularization supporting arrangement for multi-vessel system |
-
2012
- 2012-10-25 CN CN2012205491858U patent/CN202948739U/en not_active Expired - Lifetime
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2014090142A1 (en) * | 2012-12-13 | 2014-06-19 | 中国核动力研究设计院 | Circuit accident exhaust system of pressurized water reactor nuclear power plant |
| CN103390435A (en) * | 2013-07-30 | 2013-11-13 | 中广核工程有限公司 | Exhaust device and method for pressure vessel of nuclear power plant reactor coolant system |
| CN103390435B (en) * | 2013-07-30 | 2016-08-24 | 中广核工程有限公司 | The exhaust apparatus of nuclear power plant reactor coolant system pressure vessel and method |
| CN105632571A (en) * | 2014-12-01 | 2016-06-01 | 上海核工程研究设计院 | Integrated reactor equipment |
| CN106887263A (en) * | 2015-12-15 | 2017-06-23 | 中国核动力研究设计院 | The secondary laterally opened Heat Discharging System of Chinese of once through steam generator |
| CN108346476A (en) * | 2018-03-30 | 2018-07-31 | 中广核研究院有限公司 | Reactor and divide pot type voltage-stablizer |
| CN108346476B (en) * | 2018-03-30 | 2024-03-22 | 中广核研究院有限公司 | Reactor and split-tank voltage stabilizer |
| CN108986933A (en) * | 2018-08-01 | 2018-12-11 | 中广核研究院有限公司 | Modularization supporting arrangement for multi-vessel system |
| CN108986933B (en) * | 2018-08-01 | 2023-12-22 | 中广核研究院有限公司 | Modular support device for multi-container systems |
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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: 20130522 |