CN212516581U - Reactor coolant loop system of nuclear power station - Google Patents
Reactor coolant loop system of nuclear power station Download PDFInfo
- Publication number
- CN212516581U CN212516581U CN202021268357.5U CN202021268357U CN212516581U CN 212516581 U CN212516581 U CN 212516581U CN 202021268357 U CN202021268357 U CN 202021268357U CN 212516581 U CN212516581 U CN 212516581U
- Authority
- CN
- China
- Prior art keywords
- reactor coolant
- main pipeline
- steam generator
- section
- reactor
- Prior art date
- 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.)
- Active
Links
Images
Classifications
-
- 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
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a reactor coolant loop system of a nuclear power station, which comprises a reactor pressure vessel (1), a steam generator (2), a reactor coolant pump (3), a main pipeline hot section (5) and a main pipeline cold section (4); the steam generator (2) is vertically connected with the reactor coolant pump (3) below; the vertical lower part of the steam generator (2) is also connected with one end of the main pipeline hot section (5), and the other end of the main pipeline hot section (5) is connected with the reactor pressure vessel (1); one end of the main pipeline cold section (4) is connected with the reactor coolant pump (3), and the other end of the main pipeline cold section (4) is connected with the reactor pressure vessel (1); the cold section (4) of the main pipeline is higher than the hot section (5) of the main pipeline. This design saving equipment cost, reduction arrange the space, promote economic nature to be convenient for develop the maintenance activity.
Description
Technical Field
The utility model belongs to nuclear power station reactor coolant system field especially relates to reactor coolant loop field.
Background
The reactor coolant system of the pressurized water reactor nuclear power station is also called a primary coolant system, and is a system which takes heat generated by a reactor core out of a reactor, transfers the heat to the secondary side of a steam generator to generate high-temperature saturated steam, and transmits the steam to a steam and energy conversion system to convert the steam and energy into electric energy. The scheme of the second generation pressurized water reactor nuclear power unit reactor coolant system is widely applied to the scheme of a second loop, a third loop and a fourth loop, so that the output electric power of a power plant is improved. Each loop of a typical reactor coolant system includes a steam generator, a reactor coolant pump, a hot leg, a cold leg, and a transition leg connecting the steam generator and the reactor coolant pump; each loop of a reactor coolant system of a third-generation passive pressurized water reactor nuclear power unit comprises a steam generator, two reactor coolant pumps, a hot section and two cold sections, a transition section between the steam generator and the reactor coolant pumps is omitted, and a mode that the two reactor coolant pumps are directly connected with a bottom head of the steam generator is adopted. If the number of reactor coolant pumps and main pipelines on a single loop is reduced, the equipment cost is further saved, the arrangement space is reduced, and the economical efficiency is improved.
The invention aims to provide a reactor coolant loop system of a nuclear power station, which reduces the number of reactor coolant pumps and main pipelines on a single loop, reduces the loop resistance, effectively reduces the difficulties of equipment manufacture and mechanical analysis, further saves the equipment cost, reduces the arrangement space and improves the economy.
Disclosure of Invention
The invention aims to provide a reactor coolant loop system of a nuclear power station, which comprises a reactor pressure vessel (1), a steam generator (2), a reactor coolant pump (3), a main pipeline hot section (5) and a main pipeline cold section (4);
the steam generator (2) is vertically connected with the reactor coolant pump (3) below; the vertical lower part of the steam generator (2) is also connected with one end of the main pipeline hot section (5), and the other end of the main pipeline hot section (5) is connected with the reactor pressure vessel (1); one end of the main pipeline cold section (4) is connected with the reactor coolant pump (3), and the other end of the main pipeline cold section (4) is connected with the reactor pressure vessel (1); the cold section (4) of the main pipeline is higher than the hot section (5) of the main pipeline.
Preferably, the bottom of the steam generator (2) is divided into a hot chamber and a cold chamber, the cold chamber is connected with the reactor coolant pump (3), and the hot chamber is connected with the hot section (5) of the main pipeline.
Preferably, the nozzle of the steam generator (2) and the reactor coolant pump (3) and the nozzle of the steam generator (2) and the main pipe hot section (5) are the same in structure.
Preferably, two steam generator vertical supports (6) are arranged at the bottom of the steam generator (2) to bear loads under different working conditions.
Preferably, the main pipeline hot section (5) is provided with a bent pipe.
The reactor coolant loop system of the nuclear power station is characterized in that 1 steam generator, 1 reactor coolant pump, 1 hot section and 1 cold section are arranged on a single loop of the reactor coolant system, and the resistance of the loop is reduced by adopting a direct connection mode of a bottom head of the steam generator and the reactor coolant pump. The structure of the steam generator is similar to that of the reactor coolant pump, and the structure of the hot section is similar to that of the reactor coolant pump, so that the arrangement design of the lower seal head filler neck and the manhole of the steam generator is facilitated, and the manufacture of the lower seal head of the steam generator is facilitated. Meanwhile, the filler neck is vertically arranged downwards, so that the thermal expansion balance of the cold and hot sections of the main pipeline is facilitated, and the stress of the filler neck of the main equipment is reduced. The bottom of the steam generator is provided with two vertical upright supports for bearing loads under different working conditions. The cold section and the hot section of the main pipeline are provided with a certain height difference, and the hot section still keeps a certain liquid level to establish a cooling channel while the reactor coolant of the cold section is emptied during shutdown and refueling. The design further saves equipment cost, reduces arrangement space and improves economy.
Drawings
FIG. 1 is a top plan view of a reactor coolant system loop configuration for a nuclear power plant;
FIG. 2 is a front view of a reactor coolant system loop configuration for a nuclear power plant;
FIG. 3 is a side view of a reactor coolant system loop configuration for a nuclear power plant;
wherein: 1-reactor pressure vessel; 2-a steam generator; 3-reactor coolant pump; 4-main pipeline cold section; 5-hot section of main pipeline; and 6, vertically supporting the steam generator.
Detailed Description
In order to make the aforementioned objects, features and advantages of the present invention comprehensible, embodiments accompanied with figures are described in further detail below.
A reactor coolant loop system of a nuclear power station is arranged in a containment and mainly comprises a pressure vessel 1, a steam generator 2, a reactor coolant pump 3, a steam generator vertical support 6 and the like. During the power operation of the unit, the reactor coolant pump 3 pumps the reactor coolant into the reactor pressure vessel 1 through the main pipeline cold section 4, absorbs the heat of the reactor core, then enters the steam generator 2 through the main pipeline hot section 5, and transfers the heat to the secondary side water supply of the steam generator 2. The cooled reactor coolant enters the reactor coolant pump 3 to complete the circulation.
The bottom head of the steam generator 2 is divided into a hot chamber and a cold chamber, a nozzle of the cold chamber which is vertically downward is directly connected with a reactor coolant pump 3, a connecting pipeline between the steam generator 2 and the reactor coolant pump 3 is cancelled, and the pipeline and the resistance are reduced. The vertically downward pipe nozzle of the hot cavity chamber is connected with the hot section 5 of the main pipeline, and the hot section 5 of the main pipeline is provided with a bent pipe, so that the hot expansion balance of the cold and hot sections of the main pipeline is facilitated, and the stress of the pipe nozzle of the main equipment is reduced. The pipe connecting ports of the steam generator 2 and the reactor coolant pump 3 and the pipe connecting port of the main pipeline hot section 5 are designed into similar structural patterns, which is beneficial to the design of the bottom seal head pipe connecting port and the manhole of the steam generator 2 and the manufacture of the bottom seal head of the steam generator 2. Two vertical upright supports are arranged at the bottom of the steam generator 2 and are used for bearing loads under different working conditions. The main pipeline cold section 4 and the main pipeline hot section 5 are provided with certain height difference, and after the reactor coolant of the main pipeline cold section 4 is emptied during shutdown and refueling, the main pipeline hot section 5 still keeps certain liquid level and can establish a cooling channel so as to carry out maintenance activities.
The single loop configuration of the reactor coolant system adopts a mode that a bottom head of a steam generator 2 is directly connected with a reactor coolant pump 3. The pipe connecting nozzles of the steam generator 2 and the reactor coolant pump 3 and the pipe connecting nozzle of the main pipeline hot section 5 are designed into similar vertical downward structural patterns, so that the manufacture of a lower end socket of the steam generator 2 is facilitated, and the thermal expansion balance of the main pipeline cold section 4 and the main pipeline hot section 5 is facilitated. The bottom of the steam generator is provided with two vertical upright supports for bearing loads under different working conditions. The setting that the hot section of trunk line 5 is less than the cold section of trunk line 4 is so that overhaul the activity with 4 water exhaust of the cold section of trunk line during the reloading, and equipment cost is further practiced thrift in this design, the space is arranged in the reduction, promotes economic nature.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations. The foregoing examples or embodiments are merely illustrative of the present invention, which may be embodied in other specific forms or in other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.
Claims (5)
1. A reactor coolant loop system of a nuclear power station is characterized by comprising a reactor pressure vessel (1), a steam generator (2), a reactor coolant pump (3), a main pipeline hot section (5) and a main pipeline cold section (4);
the steam generator (2) is vertically connected with the reactor coolant pump (3) below; the vertical lower part of the steam generator (2) is also connected with one end of the main pipeline hot section (5), and the other end of the main pipeline hot section (5) is connected with the reactor pressure vessel (1); one end of the main pipeline cold section (4) is connected with the reactor coolant pump (3), and the other end of the main pipeline cold section (4) is connected with the reactor pressure vessel (1); the cold section (4) of the main pipeline is higher than the hot section (5) of the main pipeline.
2. The reactor coolant loop system of a nuclear power plant as set forth in claim 1, characterized in that the steam generator (2) is divided at the bottom into a hot chamber and a cold chamber, the cold chamber being connected to the reactor coolant pump (3), and the hot chamber being connected to the main pipe hot leg (5).
3. The reactor coolant loop system of a nuclear power plant as claimed in claim 1, characterized in that the filler neck of the steam generator (2) and the reactor coolant pump (3) and the filler neck of the steam generator (2) and the main pipe hot leg (5) are of the same construction.
4. The nuclear power plant reactor coolant loop system of claim 1 characterized in that two steam generator vertical supports (6) are provided at the bottom of the steam generator (2) to support the load under different operating conditions.
5. A reactor coolant loop system for nuclear power plants according to claim 1, characterized in that the main pipe hot section (5) is provided with bends.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202021268357.5U CN212516581U (en) | 2020-07-02 | 2020-07-02 | Reactor coolant loop system of nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202021268357.5U CN212516581U (en) | 2020-07-02 | 2020-07-02 | Reactor coolant loop system of nuclear power station |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN212516581U true CN212516581U (en) | 2021-02-09 |
Family
ID=74432902
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202021268357.5U Active CN212516581U (en) | 2020-07-02 | 2020-07-02 | Reactor coolant loop system of nuclear power station |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN212516581U (en) |
-
2020
- 2020-07-02 CN CN202021268357.5U patent/CN212516581U/en active Active
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN101620892B (en) | Structural design of loop system of high-power pressurized water reactor nuclear power station | |
| CN107100684A (en) | A kind of steam power plant utilizes boiler bypass depth of round peak regulation modernization system | |
| US20220415527A1 (en) | Combined power generation system and method of small fluoride-salt-cooled high-temperature reactor and solar tower | |
| CN202948739U (en) | Integrated pressurized water reactor coolant system | |
| US20200131925A1 (en) | Turbogenerator set | |
| CN102606340B (en) | Power generation system for driving Stirling engine by using heat of spent fuel | |
| CN210106020U (en) | Waste heat utilization Stirling power generation system of industrial furnace | |
| CN212516581U (en) | Reactor coolant loop system of nuclear power station | |
| CN204373272U (en) | A kind of direct contact type boiling heat exchanger | |
| CN113432176A (en) | Stepped heat storage device and hot water system | |
| CN103310856B (en) | A kind of presurized water reactor electricity generation system with inherent safety | |
| CN111271875A (en) | Water heating device utilizing solar energy and wind energy | |
| CN201503005U (en) | Primary side four-chamber two-way flow heat exchange tube pressured water reactor steam generator | |
| CN206694080U (en) | A kind of steam power plant utilizes boiler bypass depth of round peak regulation modernization system | |
| CN102434874B (en) | Nuclear power horizontal high-pressure water supply heater and heating method | |
| CN203024132U (en) | March-type anti-vibration strip structure for pressurized water reactor nuclear power plant steam generator | |
| CN109059312B (en) | Multi-tank type heat storage device and method for fused salt storage tank of photo-thermal power station | |
| CN112282875A (en) | Factory-level multi-unit coupling combined transportation system for improving flexibility of thermal power generating unit | |
| CN111508626A (en) | Three-loop reactor coolant system suitable for ultra-large pressurized water reactor | |
| CN212777950U (en) | Energy-saving device of organic heat carrier boiler | |
| CN201421066Y (en) | Secondary steam generator of closed circulating phase change heat supply system of industrial boiler | |
| CN213574263U (en) | Factory-level multi-unit coupling combined transportation system for improving flexibility of thermal power generating unit | |
| CN210197454U (en) | Heat storage tank supporting structure for peak shaving of thermal power plant | |
| CN221002879U (en) | Steam power generation device | |
| CN219529104U (en) | Solar photo-thermal and thermal generator set coupled power generation system |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
|
| CP01 | Change in the name or title of a patent holder |