CN203026160U - Pressurized water type nuclear reactor core internal - Google Patents
Pressurized water type nuclear reactor core internal Download PDFInfo
- Publication number
- CN203026160U CN203026160U CN2012207295151U CN201220729515U CN203026160U CN 203026160 U CN203026160 U CN 203026160U CN 2012207295151 U CN2012207295151 U CN 2012207295151U CN 201220729515 U CN201220729515 U CN 201220729515U CN 203026160 U CN203026160 U CN 203026160U
- Authority
- CN
- China
- Prior art keywords
- pressure vessel
- reactor core
- hanging basket
- pile component
- web joint
- 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.)
- Withdrawn - After Issue
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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model relates to the technical field of nuclear power and in particular discloses a pressurized water type nuclear reactor core internal. The pressurized water type nuclear reactor core internal comprises an upper reactor core internal and a lower reactor core internal, wherein the upper reactor core internal comprises a measuring guide structure, a straight-insertion type water level detector guide structure, an upper reactor core plate and an upper supporting plate; the lower reactor core internal comprises a basket assembly, a secondary support and a flow distribution assembly. According to the pressurized water type nuclear reactor core internal disclosed by the utility model, the lower chamber flow distribution structure is designed, the measuring guide structure in an upper end enclosure of the pressure container is adopted and the guide structure of the straight-insertion type water level detector guide structure for measuring the water level is designed, so that the reactor core internal in the pressure container can be used for uniformly distributing a reactor core cooling agent, and therefore, the integral performances of the reactor are improved and the reactor structure is simplified. Besides, the straight-insertion type water level detector guide structure is designed, so that the problem due to the fact that the water level detector is difficult to bend in the reactor because of the large diameter is solved.
Description
Technical field
The utility model belongs to the nuclear power technology field, is specifically related to reactor core internals.
Background technology
The ACP1000 pressurized water nuclear reactor has adopted 177 group fuel assemblies to form reactor core, and general existing pressurized water nuclear reactor adopts 157 group fuel assemblies as reactor core, has perhaps adopted group fuel assembly more than 200 as reactor core.
At present in two generations of operation and two generation modified pressurized water nuclear reactors, reactor core neutron flux measurement detector is drawn from the pressure vessel low head, therefore be provided with the parts such as instrumentation thimble and penetration piece at the low head place, these instrumentation thimbles, penetration piece can mix to suppress to the coolant flow field of lower chambers the formation of eddy current together with structures such as screen work plate, secondary support columns, simultaneously the flow that enters reactor core are carried out uniform distribution.Yet the existence of low head place penetration piece increased the risk of low head potential failure, and the lower chambers structure is very complicated.ACP1000 presurized water reactor neutron flux measurement detector and temperature survey detector have detailed construction to describe in the patent of application number CN200980150445.5 by measuring this structure of guide frame 1() drawn by the pressure vessel upper cover, simplified to a great extent reactor lower chambers structure, but will cause reactor core entrance area flow field generation unevenness, therefore, for satisfying the requirement of the cooling medium uniform distribution that enters reactor core, promote the reactor overall performance, need to a kind of flow distribution device be set in the reactor lower chambers.
Nuclear reactor is under normal operation or accident conditions, for the measurement data of reactor core Neutron flux distribution, fuel assembly outlet and reactor pressure vessel upper cover chamber internal reaction reactor coolant temperature and reactor pressure vessel water level is provided online, neutron flux measurement detector, temperature survey detector and water level detector need to be introduced in reactor by suitable structure.
The existing nuclear power reactor of pressurized water type dispersed placement, mostly adopt the guide frame that detector cluster type integral body is drawn, this guide frame requires detector to possess certain crooking ability, namely possess certain bending radius and angle of turn, require simultaneously reactor structure upper cover chamber to possess certain axial height.
But because the water level detector diameter is larger, be difficult to bending in heap, so the guide frame of direct insertion type water level detector need to be set.
Summary of the invention
The purpose of this utility model is to provide a kind of pressurized water nuclear reactor in-pile component that can reasonable distribution enters the coolant flow of reactor core.
Realize that the technical solution of the utility model is as follows:
a kind of pressurized water nuclear reactor in-pile component, it comprises top in-pile component and the bottom in-pile component that is arranged on pressure vessel inside, described top in-pile component comprises the measurement guide frame that arranges in the pressure vessel upper cover and the guide frame of direct insertion type water level detector, also comprise upper core plate, upper bearing plate, described upper core plate is positioned at the below of upper bearing plate, be provided with control rod guide cylinder and upper support post between upper core plate and upper bearing plate, described measurement guide frame vertically is located on upper bearing plate, the guide frame of described direct insertion type water level detector comprises the screen work plate that is located on upper bearing plate, vertically be fixed on the guidepost between screen work plate and pressure vessel upper cover and be located at upper core plate and the screen work plate between support column, described bottom in-pile component comprises hanging basket assembly and secondary supporting and assignment of traffic assembly, and described secondary supporting and assignment of traffic assembly fixedly are located at the below of hanging basket assembly, the supporting of described secondary and assignment of traffic assembly comprise the web joint, energy absorber of flow distribution baffle, flow distribution baffle below and the basic web joint of web joint below, described flow distribution baffle is fixed on below the hanging basket assembly by joint pin, web joint is fixed on below the hanging basket assembly by the secondary support column, described basic web joint is fixed in the pressure vessel low head, and described energy absorber is located between web joint and basic web joint.
In above-mentioned pressurized water nuclear reactor in-pile component, the external diameter of described flow distribution baffle is 1 ~ 2 times of pressure vessel inside radius, and its thickness of slab is 0.01～0.05 times of the inside radius of pressure vessel.
In above-mentioned pressurized water nuclear reactor in-pile component, the hanging basket of described hanging basket assembly is porose in the coolant outlet position processing corresponding to pressure vessel, the hanging basket flange of hanging basket assembly upper end is positioned on the supporting step of pressure vessel, and compresses by holddown spring; The flange of described upper bearing plate closely is pressed in the upper surface of holddown spring.
the obtained beneficial effect of the utility model is as follows: the utility model has designed novel lower chambers assignment of traffic structure, and adopted the measurement guide frame that is positioned at the pressure vessel upper cover, designed simultaneously the guide frame that is used for the direct insertion type water level detector of level measuring, make in pressure vessel the in-pile component can the agent of uniform distribution Core cooling, thereby promote the reactor overall performance, simplified reactor structure, designed in addition the guide frame of direct insertion water level detector, also solved the water level detector diameter larger, be difficult to the crooked problem of bringing in heap.
The reactor core internals of the utility model design, 177 group fuel assemblies can be held and support to its structure; Can realize that with neutron flux measurement detector and the temperature survey detector measurement guide frame by being positioned at the pressure vessel upper cover and pressure vessel top penetration piece draws the requirement of reactor; Can realize the level measuring requirement by the guide frame of direct insertion type water level detector; Simultaneously, under the precondition that realizes the in-pile component proper function, reasonable distribution enters the coolant flow of reactor core.
Description of drawings
Fig. 1 is top in-pile component schematic diagram;
Fig. 2 is bottom in-pile component schematic diagram;
Fig. 3 is the vertical view of Fig. 2;
Fig. 4 is the guide frame schematic diagram of direct insertion type water level detector;
Fig. 5 is secondary supporting and assignment of traffic assembly schematic diagram;
Fig. 6 is pressurized water nuclear reactor in-pile component structure collectivity schematic diagram of the present utility model;
In figure: 1. measure guide frame; 2. upper bearing plate; 3. control rod guide cylinder; 4. upper core plate; 5. the guide frame of direct insertion type water level detector; 6. upper support post; 7. hanging basket assembly; 8. secondary supports and the assignment of traffic assembly; 9. pressure vessel upper cover; 10. guidepost; 11. screen work plate; 12. support column; 13. joint pin; 14. flow distribution baffle; 15. secondary support column; 16. web joint; 17. energy absorber; 18. basic web joint; 19. pressure vessel low head; 20. holddown spring; 21. top in-pile component; 22. bottom in-pile component; 23. pressure vessel.
Embodiment
Below in conjunction with the drawings and specific embodiments, the utility model is described in detail.
The structure of top in-pile component 21 as shown in Figure 1, install the support column 12 of the guide frame 5 of support column 6 and direct insertion type water level detector on upper core plate 4, install support plate 2 by upper support post 6 and support column 12 supportings, all be processed with pilot hole on described upper bearing plate 2 and upper core plate 4, control rod guide cylinder 3 is installed the position of pilot hole between support plate 2 and upper core plate 4, and pass upper bearing plate 2, also vertically install and measure guide frame 1 on upper bearing plate 5.
As Fig. 2, Fig. 3 and shown in Figure 6, bottom in-pile component 22 comprises hanging basket assembly 7 and secondary supporting and assignment of traffic assembly 8, described hanging basket assembly 7 is used for holding and the supporting fuel assembly, by bolt, secondary supporting and assignment of traffic assembly 8 are installed below hanging basket assembly 7, hanging basket assembly 7 is porose in the coolant outlet position processing corresponding to pressure vessel 23.
As shown in Figure 5, described secondary supporting and assignment of traffic assembly 8 mainly are comprised of joint pin 13, flow distribution baffle 14, secondary support column 15, web joint 16, energy absorber 17, basic web joint 18.Described secondary support column 15 is bolted and is fixed on web joint 16 on hanging basket assembly 7 and prevents that it from producing vibration, the Main Function of web joint 16 is that cooling medium is mixed, suppress the formation of eddy current, and joint pin 13 connects by bolt and is fixed on flow distribution baffle 14 on hanging basket assembly 7 and prevents that it from producing vibration, and the effect of flow distribution baffle 14 is mainly that the flow that enters reactor core is carried out uniform distribution.Energy absorber 17 is bolted between web joint 16 and basic web joint 18.In the middle of this enforcement, the external diameter of flow distribution baffle 14 is 1.6 times of pressure vessel 23 inside radiuss, and thickness of slab is 0.03 times of the inside radius of pressure vessel 23.
As shown in Figure 6, the flange of described hanging basket assembly 7 upper ends is hung on the supporting step of pressure vessel 23, and holddown spring 20 is positioned on the flange of hanging basket assembly 7.The flange of described upper bearing plate 2 closely is pressed in the upper surface of holddown spring 20.The upper core plate 4 of described upper bearing plate 2, upper support post 6 and below all is positioned at the inside of hanging basket assembly 7.The upper end of above-mentioned control rod guide cylinder 3 is positioned at pressure vessel upper cover 9, measures guide frame 1 and passes pressure vessel upper cover 9 by the mounting hole of processing on pressure vessel upper cover 9.
The secondary supporting and the assignment of traffic assembly 8 that are positioned at pressure vessel 23 bottoms are mixed the cooling medium that enters reactor core together with pressure vessel low head 19, suppressing eddy current produces, and reasonable distribution enters the coolant flow of reactor core, and secondary supporting and assignment of traffic assembly 8 are bolted in hanging basket assembly 7 bottoms; Whole top in-pile component 21 is used for compressing fuel assembly; The guide frame 5 of direct insertion type water level detector is used to level measuring that passage is provided; Measuring guide frame 1 is used for neutron flux measurement detector and temperature survey detector are drawn reactor from the pressure vessel upper cover by pressure vessel top penetration piece.
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 (3)
1. pressurized water nuclear reactor in-pile component, it comprises top in-pile component (21) and the bottom in-pile component (22) that is arranged on pressure vessel (23) inside, it is characterized in that: described top in-pile component (21) comprises the measurement guide frame (1) that arranges in pressure vessel upper cover (9) and the guide frame (5) of direct insertion type water level detector, also comprise upper core plate (4), upper bearing plate (2), described upper core plate (4) is positioned at the below of upper bearing plate (2), be provided with control rod guide cylinder (3) and upper support post (6) between upper core plate (4) and upper bearing plate (2), described measurement guide frame (1) vertically is located on upper bearing plate (5), the guide frame of described direct insertion type water level detector (5) comprises the screen work plate (11) that is located on upper bearing plate (2), vertically be fixed on the guidepost (10) between screen work plate (11) and pressure vessel upper cover (9) and be located at upper core plate (4) and screen work plate (11) between support column (12), described bottom in-pile component (22) comprises hanging basket assembly (7) and secondary supporting and assignment of traffic assembly (8), and described secondary supporting and assignment of traffic assembly (8) fixedly are located at the below of hanging basket assembly (7), described secondary supporting and assignment of traffic assembly (8) comprise flow distribution baffle (14), the web joint (16) of flow distribution baffle (14) below, basic web joint (18) below energy absorber (17) and web joint (16), described flow distribution baffle (14) is fixed on below hanging basket assembly (7) by joint pin (13), web joint (16) is fixed on below hanging basket assembly (7) by secondary support column (15), described basic web joint (18) is fixed in pressure vessel low head (19), described energy absorber (17) is located between web joint (16) and basic web joint (18).
2. pressurized water nuclear reactor in-pile component as claimed in claim 1, it is characterized in that: the external diameter of described flow distribution baffle (14) is 1 ~ 2 times of pressure vessel (23) inside radius, its thickness of slab is 0.01～0.05 times of the inside radius of pressure vessel (23).
3. pressurized water nuclear reactor in-pile component as claimed in claim 1, it is characterized in that: the hanging basket of described hanging basket assembly (7) is porose in the coolant outlet position processing corresponding to pressure vessel (23), the hanging basket flange of hanging basket assembly (7) upper end is positioned on the supporting step of pressure vessel (23), and compresses by holddown spring (20); The flange of described upper bearing plate (2) closely is pressed in the upper surface of holddown spring (20).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012207295151U CN203026160U (en) | 2012-12-26 | 2012-12-26 | Pressurized water type nuclear reactor core internal |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012207295151U CN203026160U (en) | 2012-12-26 | 2012-12-26 | Pressurized water type nuclear reactor core internal |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN203026160U true CN203026160U (en) | 2013-06-26 |
Family
ID=48650126
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2012207295151U Withdrawn - After Issue CN203026160U (en) | 2012-12-26 | 2012-12-26 | Pressurized water type nuclear reactor core internal |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN203026160U (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103366843A (en) * | 2013-07-22 | 2013-10-23 | 中国核动力研究设计院 | Guiding structure of straight inserted detector for nuclear reactor |
| CN103390437A (en) * | 2013-07-22 | 2013-11-13 | 中国核动力研究设计院 | Liquid-gas separation structure and water level detector guiding structure comprising the liquid-gas separation structure |
| CN103903656A (en) * | 2012-12-26 | 2014-07-02 | 中国核动力研究设计院 | Reactor internals of pressurized water nuclear reactor |
| CN105719707A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Differential pressure measuring point layout structure in pressurized water reactor integral hydraulic simulation test |
| CN107093481A (en) * | 2017-06-01 | 2017-08-25 | 中国核工业第五建设有限公司 | The method for making in-pile component positioning insert in AP1000 nuclear power stations |
-
2012
- 2012-12-26 CN CN2012207295151U patent/CN203026160U/en not_active Withdrawn - After Issue
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103903656A (en) * | 2012-12-26 | 2014-07-02 | 中国核动力研究设计院 | Reactor internals of pressurized water nuclear reactor |
| CN103903656B (en) * | 2012-12-26 | 2016-08-03 | 中国核动力研究设计院 | Pressurized water nuclear reactor in-pile component |
| CN103366843A (en) * | 2013-07-22 | 2013-10-23 | 中国核动力研究设计院 | Guiding structure of straight inserted detector for nuclear reactor |
| CN103390437A (en) * | 2013-07-22 | 2013-11-13 | 中国核动力研究设计院 | Liquid-gas separation structure and water level detector guiding structure comprising the liquid-gas separation structure |
| CN103366843B (en) * | 2013-07-22 | 2015-11-25 | 中国核动力研究设计院 | The guide frame of the direct insertion detector of a kind of nuclear reactor |
| CN103390437B (en) * | 2013-07-22 | 2016-02-10 | 中国核动力研究设计院 | The water level detector guide frame of liquid gas separation structure and formation thereof |
| CN105719707A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Differential pressure measuring point layout structure in pressurized water reactor integral hydraulic simulation test |
| CN107093481A (en) * | 2017-06-01 | 2017-08-25 | 中国核工业第五建设有限公司 | The method for making in-pile component positioning insert in AP1000 nuclear power stations |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN103903656B (en) | Pressurized water nuclear reactor in-pile component | |
| CN203026160U (en) | Pressurized water type nuclear reactor core internal | |
| CN104167226B (en) | Liquid metal cooling reactor experimental system capable of realizing critical and subcritical running test | |
| CN103474099B (en) | high thermal neutron fluence rate reactor core | |
| EP2227814B1 (en) | Neutron shielding panels for reactor pressure vessels | |
| CN103366843B (en) | The guide frame of the direct insertion detector of a kind of nuclear reactor | |
| CN102257575A (en) | Upper internal arrangement for a pressurized water reactor | |
| CN103871500A (en) | Nuclear reactor lower chamber cylinder-like flow distribution apparatus | |
| CN103077752A (en) | Fuel component and fixing method for liquid heavy metal cooling reactor | |
| CN103871501B (en) | Flow distributor of nuclear reactor lower chamber | |
| JP5606361B2 (en) | Guide device for neutron flux detector | |
| CN103871503A (en) | Nuclear reactor lower chamber plate-like flow distribution apparatus | |
| CN202549315U (en) | Reactor core of small reactor using 300 thousand kilowatt fuel assembly and molten iron reflecting layer | |
| JP6577014B2 (en) | Method of pulling out the in-core instrument from the core of a pressurized water reactor | |
| US4609522A (en) | Mechanical drive system for moving fuel | |
| CN202650566U (en) | Ellipsoid-type flow distributor | |
| JP2013540271A (en) | Retaining spring for nuclear fuel assembly | |
| US11798693B2 (en) | Magneto-rheological nuclear reactivity distribution control elements | |
| CN103871502A (en) | Nuclear reactor lower chamber cylindrical flow distribution apparatus | |
| CN103474106A (en) | Ellipsoid-type flow distributor | |
| CN103117098A (en) | Square fuel assembly structure suitable for supercritical water-cooled reactor | |
| CN105895171A (en) | Flow distributing structure for lower cavity of pressurized water reactor | |
| KR20080060791A (en) | Top nozzle assembly having volute spring in nuclear fuel assembly | |
| CN202650567U (en) | Pressurizer surge line for nuclear power plant | |
| CN104011801A (en) | Earthquake-resistant reinforcement assembly |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| AV01 | Patent right actively abandoned |
Granted publication date: 20130626 Effective date of abandoning: 20160803 |
|
| C25 | Abandonment of patent right or utility model to avoid double patenting |