CN108962409A - A kind of nuclear power plant's nested type reactor coolant pipe - Google Patents
A kind of nuclear power plant's nested type reactor coolant pipe Download PDFInfo
- Publication number
- CN108962409A CN108962409A CN201810757949.4A CN201810757949A CN108962409A CN 108962409 A CN108962409 A CN 108962409A CN 201810757949 A CN201810757949 A CN 201810757949A CN 108962409 A CN108962409 A CN 108962409A
- Authority
- CN
- China
- Prior art keywords
- stub
- tube
- hot arc
- cold section
- hot
- 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
- 239000002826 coolant Substances 0.000 title claims abstract description 42
- 238000012546 transfer Methods 0.000 claims abstract description 4
- 238000013461 design Methods 0.000 abstract description 6
- 238000009434 installation Methods 0.000 description 4
- 238000012360 testing method Methods 0.000 description 3
- 230000008646 thermal stress Effects 0.000 description 3
- 238000004519 manufacturing process Methods 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/22—Structural association of coolant tubes with headers
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
It is an object of the invention to disclose a kind of nuclear power plant's nested type reactor coolant pipe, it includes hot arc and cold section, and the hot arc is made of hot arc straight section and hot leg elbow, and described cold section is made of cold section of stub (tube) of cold section of stub (tube) of pressure vessel and main pump；Cold section of stub (tube) of main pump transfers out coolant from main pump outlet, and coolant is delivered in reactor by cold section of stub (tube) of pressure vessel；Hot arc straight section exports coolant to hot arc straight section through hanging basket hot arc stub (tube), then reaches steam generator through hot leg elbow；Compared with prior art, reactor coolant is transported in steam generator by hot arc pipeline, reactor coolant is sent back to reactor pressure vessel by cold segment pipe completes circulation, save arrangement space, it realizes compact design, reduces workshop occupancy, it is reproducible at multiple circuits, meet different capacity demand, achieves the object of the present invention.
Description
Technical field
The present invention relates to a kind of ooling channel of nuclear power plant's reactor coolant loop, in particular to a kind of nuclear power plant is anti-
Answer nuclear power plant's nested type reactor coolant pipe of reactor coolant system.
Background technique
In nuclear power plant in reactor coolant loop, reactor coolant pipe (hereinafter referred to as main pipeline) is as reaction
The runner of reactor coolant, be pressure boundary particularly important in primary Ioops reactor coolant loop and prevent primary Ioops substance to
The safety curtain of external leakage.
Reactor coolant pipe (hereinafter referred to as main pipeline) is usually made of hot arc and cold section, hot arc connection reaction stacking pressure
Force container (RPV) and steam generator (SG), cold section of connection reactor pressure vessel and reactor coolant pump (RCP).
The economy of nuclear power technology is great to the influence on development of each nuclear power heap-type, and workshop is assessed having a size of Technical Economy
Important parameter.Major loop arrangement space has an important influence the space of entire workshop again, and main pipeline is arranged as major loop
One of most critical element, directly affect the economy of hall space and nuclear power technology.
Summary of the invention
The purpose of the present invention is to provide a kind of nuclear power plant's nested type reactor coolant pipes, not for the prior art
Foot is suitable for two or more circuits, meets different capacity demand.
Technical problem solved by the invention can be realized using following technical scheme:
A kind of nuclear power plant's nested type reactor coolant pipe, which is characterized in that it includes hot arc and cold section, the hot arc
It is made of hot arc straight section and hot leg elbow, described cold section is made of cold section of stub (tube) of cold section of stub (tube) of pressure vessel and main pump；It is main
It pumps cold section of stub (tube) to transfer out coolant from main pump outlet, and is delivered to coolant instead by cold section of stub (tube) of pressure vessel
It answers in heap；Hot arc straight section exports coolant to hot arc straight section through hanging basket hot arc stub (tube), then reaches steam hair through hot leg elbow
Raw device.
In one embodiment of the invention, the steam generator and main pump are set as unitary member, to realize
Compact design reduces workshop occupancy, enters cold section of progress weld seam In-service testing for personnel and provides path.
In one embodiment of the invention, the hot arc straight section and hanging basket hot arc stub (tube) pass through the close card of thermal expansion
It connects, reduces the thermal stress generated by thermal expansion.
In one embodiment of the invention, the hot leg elbow is bolted with steam generator, is convenient for hot arc
Installation.
In one embodiment of the invention, led to by cold section of stub (tube) of cold section of stub (tube) of pressure vessel and main pump for described cold section
Welded connecting is crossed to be formed, it can be achieved that higher manufacture and installation accuracy.
Nuclear power plant's nested type reactor coolant pipe of the invention compared with prior art will be anti-by hot arc pipeline
It answers reactor coolant to be transported in steam generator, reactor pressure vessel back to is sent reactor coolant by cold segment pipe and is completed
Circulation saves arrangement space, realizes compact design, reduces workshop occupancy, reproducible at multiple circuits, meets different capacity
Demand achieves the object of the present invention.
The features of the present invention sees the detailed description of the drawings of the present case and following preferable embodiment and obtains clearly
Solution.
Detailed description of the invention
Fig. 1 is the structural schematic diagram of nuclear power plant's nested type reactor coolant pipe of the invention.
Specific embodiment
In order to be easy to understand the technical means, the creative features, the aims and the efficiencies achieved by the present invention, tie below
Conjunction is specifically illustrating, and the present invention is further explained.
Embodiment 1
As shown in Figure 1, nuclear power plant's nested type reactor coolant pipe of the invention, it includes hot arc and cold section, described
Hot arc is made of hot arc straight section 1 and hot leg elbow 2, and described cold section by cold section of stub (tube) 4 of cold section of stub (tube) 3 of pressure vessel and main pump
Composition；Cold section of stub (tube) 4 of main pump transfers out coolant from main pump outlet, and will be cooled down by cold section of stub (tube) 3 of pressure vessel
Agent is delivered in reactor；Hot arc straight section 1 exports coolant to hot arc straight section 1 through hanging basket hot arc stub (tube) 5, then curved through hot arc
Pipe 2 reaches steam generator.
Nuclear power plant's nested type reactor coolant pipe connected components of the invention are pressure vessel 6, hanging basket 7, steam hair
Raw device/main pump unitary member 8.
In the present embodiment, the steam generator and main pump are set as unitary member 8, thus realize compact design,
Reduce workshop occupancy, enters cold section of progress weld seam In-service testing for personnel and path is provided.
In the present embodiment, hot arc straight section 1 and hanging basket hot arc stub (tube) 5 are reduced by thermal expansion tight clamping fit because of heat
Expand the thermal stress generated.
In the present embodiment, hot leg elbow 2 is connect with steam generator by bolt 9, is installed convenient for hot arc.
In the present embodiment, connected by cold section of stub (tube) 4 of cold section of stub (tube) 3 of pressure vessel and main pump by welding for described cold section
It connects to be formed, it can be achieved that higher manufacture and installation accuracy.
Nuclear power plant's nested type reactor coolant pipe of the invention is suitable for two or more circuits；Hot arc pipeline will
Reactor coolant is transported in steam generator；Cold segment pipe is sent reactor coolant back to reactor pressure vessel completion and is followed
Ring.
Nuclear power plant's nested type reactor coolant pipe of the invention has following technological merit:
1) main pipe hot leg is nested in cold section of main pipeline, saves arrangement space, reduces equipment pipe nozzle.
2) hot arc with hanging basket hot arc stub (tube) pass through thermal expansion tight clamping fit during operation, reduce because thermal expansion produces
Raw thermal stress.
3) hot arc is connected by screw bolts with steam generator, is installed convenient for hot arc.
4) it is directly welded and is formed, it can be achieved that higher system by cold section of stub (tube) of cold section of stub (tube) of pressure vessel and main pump for cold section
It makes and installation accuracy.
5) steam generator and main pump are integrated component, to realize compact design, reduce workshop occupancy.
6) pump case is connected directly with cold section, is entered cold section of progress weld seam In-service testing for personnel and is provided path.
7) design of compact nested type main pipeline is reproducible at multiple circuits, meets different capacity demand.
The above shows and describes the basic principles and main features of the present invention and the advantages of the present invention.The technology of the industry
Personnel are it should be appreciated that the present invention is not limited to the above embodiments, and the above embodiments and description only describe this
The principle of invention, without departing from the spirit and scope of the present invention, various changes and improvements may be made to the invention, these changes
Change and improvement all fall within the protetion scope of the claimed invention, the claimed scope of the invention by appended claims and its
Equivalent thereof.
Claims (5)
1. a kind of nuclear power plant's nested type reactor coolant pipe, which is characterized in that it includes hot arc and cold section, the hot arc by
Hot arc straight section and hot leg elbow composition, described cold section is made of cold section of stub (tube) of cold section of stub (tube) of pressure vessel and main pump；Main pump
Cold section of stub (tube) transfers out coolant from main pump outlet, and coolant is delivered to reaction by cold section of stub (tube) of pressure vessel
In heap；Hot arc straight section exports coolant to hot arc straight section through hanging basket hot arc stub (tube), then reaches steam generation through hot leg elbow
Device.
2. nuclear power plant's nested type reactor coolant pipe as described in claim 1, which is characterized in that the steam generator
Unitary member is set as with main pump.
3. nuclear power plant's nested type reactor coolant pipe as described in claim 1, which is characterized in that the hot arc straight section with
Hanging basket hot arc stub (tube) passes through thermal expansion tight clamping fit.
4. nuclear power plant's nested type reactor coolant pipe as described in claim 1, which is characterized in that the hot leg elbow with
Steam generator is bolted.
5. nuclear power plant's nested type reactor coolant pipe as described in claim 1, which is characterized in that described cold section by pressure
Cold section of stub (tube) of cold section of stub (tube) of container and main pump is formed by being welded to connect.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810757949.4A CN108962409A (en) | 2018-07-11 | 2018-07-11 | A kind of nuclear power plant's nested type reactor coolant pipe |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810757949.4A CN108962409A (en) | 2018-07-11 | 2018-07-11 | A kind of nuclear power plant's nested type reactor coolant pipe |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN108962409A true CN108962409A (en) | 2018-12-07 |
Family
ID=64482889
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201810757949.4A Pending CN108962409A (en) | 2018-07-11 | 2018-07-11 | A kind of nuclear power plant's nested type reactor coolant pipe |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN108962409A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110111914A (en) * | 2019-04-28 | 2019-08-09 | 中广核研究院有限公司 | A kind of nuclear reactor and its in-pile component |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102859606A (en) * | 2010-02-05 | 2013-01-02 | 斯姆尔有限公司 | Nuclear reactor system having natural circulation of primary coolant |
| CN105321584A (en) * | 2014-07-17 | 2016-02-10 | 尼古拉斯·M·博诺姆 | Containment for a water cooled and moderated nuclear reactor |
| CN106098116A (en) * | 2016-08-11 | 2016-11-09 | 上海核工程研究设计院 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
| CN106098115A (en) * | 2016-08-11 | 2016-11-09 | 上海核工程研究设计院 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
| CN108062985A (en) * | 2017-12-28 | 2018-05-22 | 中广核研究院有限公司 | For the pressure vessel of reactor |
| CN208889338U (en) * | 2018-07-11 | 2019-05-21 | 上海核工程研究设计院有限公司 | A kind of nuclear power plant's nested type reactor coolant pipe |
-
2018
- 2018-07-11 CN CN201810757949.4A patent/CN108962409A/en active Pending
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102859606A (en) * | 2010-02-05 | 2013-01-02 | 斯姆尔有限公司 | Nuclear reactor system having natural circulation of primary coolant |
| CN105321584A (en) * | 2014-07-17 | 2016-02-10 | 尼古拉斯·M·博诺姆 | Containment for a water cooled and moderated nuclear reactor |
| CN106098116A (en) * | 2016-08-11 | 2016-11-09 | 上海核工程研究设计院 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
| CN106098115A (en) * | 2016-08-11 | 2016-11-09 | 上海核工程研究设计院 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
| CN108062985A (en) * | 2017-12-28 | 2018-05-22 | 中广核研究院有限公司 | For the pressure vessel of reactor |
| CN208889338U (en) * | 2018-07-11 | 2019-05-21 | 上海核工程研究设计院有限公司 | A kind of nuclear power plant's nested type reactor coolant pipe |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110111914A (en) * | 2019-04-28 | 2019-08-09 | 中广核研究院有限公司 | A kind of nuclear reactor and its in-pile component |
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| PB01 | 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 Co.,Ltd. |
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| CB02 | Change of applicant information |