CN106098109A - A kind of nuclear reactor system - Google Patents
A kind of nuclear reactor system Download PDFInfo
- Publication number
- CN106098109A CN106098109A CN201610523496.XA CN201610523496A CN106098109A CN 106098109 A CN106098109 A CN 106098109A CN 201610523496 A CN201610523496 A CN 201610523496A CN 106098109 A CN106098109 A CN 106098109A
- Authority
- CN
- China
- Prior art keywords
- steam generator
- pressure vessel
- reactor system
- nuclear reactor
- centrage
- 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.)
- Pending
Links
- 230000007423 decrease Effects 0.000 abstract description 2
- 238000000034 method Methods 0.000 description 4
- 230000004048 modification Effects 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 2
- 230000007812 deficiency Effects 0.000 description 1
- 238000013139 quantization Methods 0.000 description 1
- 238000010025 steaming Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
- G21C1/326—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed next to or beside the core
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/006—Details of nuclear power plant primary side of steam generators
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The present invention provides a kind of nuclear reactor system, and it includes reactor pressure vessel and steam generator；Described reactor pressure vessel and described steam generator are directly connected to.The nuclear reactor system that the present invention provides, is directly connected to including reactor pressure vessel and steam generator, reactor pressure vessel and steam generator.Relatively conventional reactor system, the nuclear reactor system that the present invention provides, it is achieved that reactor pressure vessel is integrated with steam generator, improves intensity and the safety of equipment, significantly decreases the volume of reactor system.
Description
Technical field
The present invention relates to a kind of nuclear reactor system.
Background technology
Generally, nuclear reactor system mainly includes reactor pressure vessel and steam generator, wherein, as it is shown in figure 1, steam
Vapour generator 2 is arranged at outside pressure vessel 1, and arranges main pipeline 3 specially and be indirectly connected with steam generator 2 by pressure vessel 1,
Intensity is low, and security performance is weak.
Summary of the invention
The present invention is directed to the deficiencies in the prior art, propose a kind of nuclear reactor system.
Nuclear reactor system includes reactor pressure vessel and steam generator；Described reactor pressure vessel and described steaming
Vapour generator is directly connected to.
Preferably, the geometric center lines of described pressure vessel is 2m-to the distance of the centrage of described steam generator
10m。
Preferably, described reactor pressure vessel is provided with the first ozzle；Described steam generator is provided with the second ozzle；Described
First ozzle and described second ozzle connect.
Preferably, the quantity of described steam generator is multiple.
Preferably, the most described reactor pressure vessel of described steam generator is arranged symmetrically with.
Preferably, the quantity of described steam generator is two；The centrage of said two steam generator with described instead
The angle answering the common vertical line of the centrage of core pressure vessel is 180 ° ± 2 °.
Preferably, the quantity of described steam generator is three；The centrage of adjacent two steam generators with described instead
The angle answering the common vertical line of the centrage of core pressure vessel is 120 ° ± 2 °.
Preferably, the quantity of described steam generator is four；The centrage of adjacent two steam generators with described instead
The angle answering the common vertical line of the centrage of core pressure vessel is 90 ° ± 2 °.
Compared with prior art, the method have the advantages that
1, the nuclear reactor system that the present invention provides, including reactor pressure vessel and steam generator, reactor pressure
Container and steam generator are directly connected to.Relatively conventional reactor system, the nuclear reactor system that the present invention provides, it is achieved that
Reactor pressure vessel is integrated with steam generator, improves intensity and the safety of equipment, significantly decreases reaction
The volume of shut-down system.
Accompanying drawing explanation
Fig. 1 is the schematic three dimensional views of tradition reactor system.
Fig. 2 is the nuclear reactor system quantity of 1 steam generator (include be) meeting the preferred embodiment of the present invention
Schematic three dimensional views.
Fig. 3 is the nuclear reactor system quantity of 2 steam generators (include be) meeting the preferred embodiment of the present invention
Schematic three dimensional views.
Fig. 4 is the top view of structure shown in Fig. 3.
Fig. 5 is the nuclear reactor system quantity of 3 steam generators (include be) meeting the preferred embodiment of the present invention
Schematic three dimensional views.
Fig. 6 is the top view of structure shown in Fig. 5.
Fig. 7 is the nuclear reactor system quantity of 4 steam generators (include be) meeting the preferred embodiment of the present invention
Schematic three dimensional views.
Fig. 8 is the top view of structure shown in Fig. 7.
Fig. 9 is the structural representation of KLT40.
Detailed description of the invention
Understandable for enabling the above-mentioned purpose of the present invention, feature and advantage to become apparent from, real with concrete below in conjunction with the accompanying drawings
The present invention is further detailed explanation to execute mode.
As in figure 2 it is shown, nuclear reactor system includes reactor pressure vessel 1 and steam generator 2；Reactor pressure vessel
1 and steam generator 2 be directly connected to.
Being directly connected to of reactor pressure vessel 1 and steam generator 2, the definition of quantization is, in the geometry of pressure vessel 1
Heart line is 2m-10m to the distance of the centrage of steam generator 2.
Reactor pressure vessel 1 is provided with the first ozzle 11；Steam generator 2 is provided with the second ozzle 21；First ozzle 11 He
Second ozzle 21 connects.
The quantity of steam generator 2 is multiple.Multiple steam generator 2 relative response core pressure vessels 1 are arranged symmetrically with.
As shown in Figures 3 and 4, the quantity of steam generator 2 is two；The centrage of two steam generators 2 and reactor
The angle of the common vertical line 9 of the centrage of pressure vessel 1 is 180 ° ± 2 °.
As it can be seen in figures 5 and 6, the quantity of steam generator 2 is three；The centrage of adjacent two steam generators 2 is with anti-
The angle answering the common vertical line 9 of the centrage of core pressure vessel 1 is 120 ° ± 2 °.
As shown in FIG. 7 and 8, the quantity of steam generator 2 is four；The centrage of adjacent two steam generators 2 is with anti-
The angle answering the common vertical line 9 of the centrage of core pressure vessel 1 is 90 ° ± 2 °.
Compared with prior art, embodiments of the invention have the advantages that
1, the nuclear reactor system that embodiments of the invention provide, including reactor pressure vessel and steam generator, instead
Core pressure vessel and steam generator is answered to be directly connected to.Relatively conventional reactor system, the nuclear reactor system that the present invention provides
System, it is achieved that reactor pressure vessel is integrated with steam generator, improves intensity and the safety of equipment, subtracts significantly
The little volume of reactor system.
The most also there are the reactor system using reactor pressure vessel to be directly connected to, such as Russia sieve with steam generator
This KLT40 (as shown in Figure 9), but it makes a marked difference with scheme disclosed in this invention.
Steam generator described in scheme disclosed in this invention, for traditional U-tube steam generator, and KLT40
The steam generator used is continuous steam generator.Steam generator of the present invention, hangs with a master bottom it
Pump, and the steam generator of KLT40 cannot be mounted directly main pump, main pump is suspended on the body of reactor pressure vessel.
In this specification, each embodiment uses the mode gone forward one by one to describe, and what each embodiment stressed is and other
The difference of embodiment, between each embodiment, identical similar portion sees mutually.For system disclosed in embodiment
For, owing to corresponding to the method disclosed in Example, so describe is fairly simple, relevant part sees method part explanation
?.
Those skilled in the art can use different methods to realize described function to each specifically should being used for, but
It is this realization it is not considered that beyond the scope of this invention.
Obviously, those skilled in the art can carry out various change and the modification spirit without deviating from the present invention to invention
And scope.So, if the present invention these amendment and modification belong to the claims in the present invention and equivalent technologies thereof scope it
In, then the present invention is also intended to change and including modification include these.
Claims (8)
1. a nuclear reactor system, it is characterised in that include reactor pressure vessel and steam generator；Described reactor pressure
Force container and described steam generator are directly connected to.
2. nuclear reactor system as claimed in claim 1, it is characterised in that the geometric center lines of described pressure vessel is to described
The distance of the centrage of steam generator is 2m-10m.
3. nuclear reactor system as claimed in claim 1, it is characterised in that described reactor pressure vessel is provided with the first pipe
Mouth；Described steam generator is provided with the second ozzle；Described first ozzle and described second ozzle connect.
4. nuclear reactor system as claimed in claim 1, it is characterised in that the quantity of described steam generator is multiple.
5. nuclear reactor system as claimed in claim 4, it is characterised in that described steam generator the most described reactor pressure
Force container is arranged symmetrically with.
6. nuclear reactor system as claimed in claim 5, it is characterised in that the quantity of described steam generator is two；Institute
The angle of the common vertical line stating the centrage of two steam generators and the centrage of described reactor pressure vessel is 180 ° ± 2 °.
7. nuclear reactor system as claimed in claim 5, it is characterised in that the quantity of described steam generator is three；Phase
The centrage of adjacent two steam generators is 120 ° ± 2 ° with the angle of the common vertical line of the centrage of described reactor pressure vessel.
8. nuclear reactor system as claimed in claim 5, it is characterised in that the quantity of described steam generator is four；Phase
The centrage of adjacent two steam generators is 90 ° ± 2 ° with the angle of the common vertical line of the centrage of described reactor pressure vessel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610523496.XA CN106098109A (en) | 2016-07-05 | 2016-07-05 | A kind of nuclear reactor system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610523496.XA CN106098109A (en) | 2016-07-05 | 2016-07-05 | A kind of nuclear reactor system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN106098109A true CN106098109A (en) | 2016-11-09 |
Family
ID=57212954
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610523496.XA Pending CN106098109A (en) | 2016-07-05 | 2016-07-05 | A kind of nuclear reactor system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN106098109A (en) |
Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5517094A (en) * | 1978-06-23 | 1980-02-06 | Bretagne Atel Chantiers | Supporting and protecting apparatus for assebled body of permanently connecting apparatus |
| FR2525378A1 (en) * | 1982-04-16 | 1983-10-21 | Alsthom Atlantique | Support frame for compact nuclear boiler - where reactor vessel and steam generators possess trunnions able to slide in hydraulic ball and socket bearings in frame to absorb shock |
| FR2750790A1 (en) * | 1996-07-08 | 1998-01-09 | Framatome Sa | NUCLEAR REACTOR COMPRISING A VESSEL IN WHICH THE REACTOR CORE IS AVAILABLE AND METHOD FOR COOLING THE REACTOR CORE ON STOP |
| US20110158371A1 (en) * | 2008-09-30 | 2011-06-30 | Kabushiki Kaisha Toshiba | Pressurized water reactor plant |
| JP2013029316A (en) * | 2011-07-26 | 2013-02-07 | Toshiba Corp | Steam generator |
| CN103489488A (en) * | 2012-06-11 | 2014-01-01 | 中国核动力研究设计院 | Module type pressurized water reactor |
| US20140189995A1 (en) * | 2011-01-19 | 2014-07-10 | Xuancui Liang | Methods for installing reactor coolant loop piping in a nuclear power plant |
| CN204665240U (en) * | 2015-03-10 | 2015-09-23 | 中科华核电技术研究院有限公司 | Steam generator water chamber head structure |
| US20160019988A1 (en) * | 2014-07-17 | 2016-01-21 | Nico M. Bonhomme | Containment for a water cooled and moderated Nuclear Reactor |
| CN105280257A (en) * | 2015-11-05 | 2016-01-27 | 中国核动力研究设计院 | Integrated small reactor |
| CN105679382A (en) * | 2016-03-25 | 2016-06-15 | 上海核工程研究设计院 | Nuclear power station primary loop main equipment direct connecting manner |
-
2016
- 2016-07-05 CN CN201610523496.XA patent/CN106098109A/en active Pending
Patent Citations (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5517094A (en) * | 1978-06-23 | 1980-02-06 | Bretagne Atel Chantiers | Supporting and protecting apparatus for assebled body of permanently connecting apparatus |
| FR2525378A1 (en) * | 1982-04-16 | 1983-10-21 | Alsthom Atlantique | Support frame for compact nuclear boiler - where reactor vessel and steam generators possess trunnions able to slide in hydraulic ball and socket bearings in frame to absorb shock |
| FR2750790A1 (en) * | 1996-07-08 | 1998-01-09 | Framatome Sa | NUCLEAR REACTOR COMPRISING A VESSEL IN WHICH THE REACTOR CORE IS AVAILABLE AND METHOD FOR COOLING THE REACTOR CORE ON STOP |
| US20110158371A1 (en) * | 2008-09-30 | 2011-06-30 | Kabushiki Kaisha Toshiba | Pressurized water reactor plant |
| US20140189995A1 (en) * | 2011-01-19 | 2014-07-10 | Xuancui Liang | Methods for installing reactor coolant loop piping in a nuclear power plant |
| JP2013029316A (en) * | 2011-07-26 | 2013-02-07 | Toshiba Corp | Steam generator |
| CN103489488A (en) * | 2012-06-11 | 2014-01-01 | 中国核动力研究设计院 | Module type pressurized water reactor |
| US20160019988A1 (en) * | 2014-07-17 | 2016-01-21 | Nico M. Bonhomme | Containment for a water cooled and moderated Nuclear Reactor |
| CN105321584A (en) * | 2014-07-17 | 2016-02-10 | 尼古拉斯·M·博诺姆 | Containment Vessels for Water-Cooled Moderated Nuclear Reactors |
| CN204665240U (en) * | 2015-03-10 | 2015-09-23 | 中科华核电技术研究院有限公司 | Steam generator water chamber head structure |
| CN105280257A (en) * | 2015-11-05 | 2016-01-27 | 中国核动力研究设计院 | Integrated small reactor |
| CN105679382A (en) * | 2016-03-25 | 2016-06-15 | 上海核工程研究设计院 | Nuclear power station primary loop main equipment direct connecting manner |
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| C06 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| CB02 | Change of applicant information |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |
|
| CB02 | Change of applicant information | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20161109 |
|
| WD01 | Invention patent application deemed withdrawn after publication |