CN101620892B - Structural design of loop system of high-power pressurized water reactor nuclear power station - Google Patents
Structural design of loop system of high-power pressurized water reactor nuclear power station Download PDFInfo
- Publication number
- CN101620892B CN101620892B CN2009100891306A CN200910089130A CN101620892B CN 101620892 B CN101620892 B CN 101620892B CN 2009100891306 A CN2009100891306 A CN 2009100891306A CN 200910089130 A CN200910089130 A CN 200910089130A CN 101620892 B CN101620892 B CN 101620892B
- Authority
- CN
- China
- Prior art keywords
- outlets
- inlets
- nuclear power
- pressurized water
- circuit system
- 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.)
- Expired - Fee Related
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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a structural design of a loop system of a high-power pressurized water reactor nuclear power station, belonging to the technical field of nuclear power energy sources. The structural design comprises a main container and two bidirectional flow heat exchange tube pressurized water reactor steam generators, wherein the main container is provided with four inlets and four outlets; the two steam generators are adopted, each steam generator is provided with two inlets and two outlets, the cooling water pumps of four reactors are respectively connected with the four outlets of the two steam generators and then are connected with the inlets of the main container by cold section main pipelines, and the four outlets of the main container are respectively connected with the four inlets of the two steam generators by four hot section main pipelines, thereby ensuring the bidirectional flow circulation and the heat transmission of cooling water in the loop system. The invention is favorable to realizing the uniformity of a flow field of an upper cavity of a reactor core of a single high-power nuclear generator group in operation and lowering the stress level at the connection tubes of the outlets of the main container, and well solves the problem of higher safety and maintenance cost existing in the power maximization of a single reactor of the pressurized water reactor nuclear generator group.
Description
Technical field
The invention belongs to the nuclear power energy technology field, particularly a kind of high-power pressurized water reactor nuclear power station one circuit system structural design.
Background technology
The major equipment of pressurized-water reactor nuclear power plant one circuit system comprises: primary tank, steam generator, cooling-water pump, and the trunk line that connects these equipment.Present be divided into four types of two generations in labour or at the arrangement of a circuit system of building pressurized-water reactor nuclear power plant.Wherein two of second generation pressurized-water reactor nuclear power plant type of one loop arrangement has: primary tank has the import of two symmetrical distributions and the outlet of two symmetrical distributions; Each outlet links to each other with the inlet of a steam generator through a hot arc trunk line respectively; Each primary tank import links to each other with cooling-water pump, steam generator outlet through a cold section trunk line respectively successively, constitutes two loop arrangements of two steam generators of primary tank two imports, two outlets with this; Second type is that primary tank has three equally distributed imports and three equally distributed outlets; Per two adjacent imports link to each other with a steam generator through one cold section, cooling-water pump, a hot arc trunk line with outlet, constitute three three loop arrangements that export three steam generators of three imports of primary tank with this.The representative loop method for arranging of third generation pressurized-water reactor nuclear power plant mainly contains two types: primary tank has four outlets of four imports (shown in Fig. 1 b); Adjacent import links to each other with a steam generator through one cold section, cooling-water pump, a hot arc trunk line with outlet, constitutes four Fourth Ring road arrangements that export four steam generators of four imports of primary tank with this; An another kind of loop arrangement rough schematic view that is China shown in Figure 1 in the first core power station of building, wherein a. is the loop arrangement rough schematic view of nuclear power station AP1000.B is a loop arrangement rough schematic view of N4 nuclear power station.Label 100 is a primary tank among the figure, and label 101 is a steam generator among Fig. 1 a, Fig. 1 b, and Fig. 1 a is that 2, Fig. 1 b are 4.Label 109 is the heat pipe section of a circuit system among Fig. 1 a, Fig. 1 b, and Fig. 1 a is that 2, Fig. 1 b are 4.Label 107,108,110 and 111 is the cold leg of a circuit system among Fig. 1 a, Fig. 1 b, and promptly primary tank 100 has four to be 107,108, the 110 circuit system imports that are connected with four cold legs of 111 with label; Steam generator adopts Δ-125 type steam generator; Label is that four cooling-water pumps of 103,104,105 and 106 are connected to a circuit system import through 107,108,110 and 111 4 cold legs, realizes the chilled water circulation of a circuit system.
If the presurized water reactor single-machine capacity of the N4 nuclear power station of the above-mentioned AP1000 nuclear power station that has only two discharge connections or four discharge connections is to the better large pressurized water reactor development of economy; The unevenness in primary tank upper chamber flow field will further be aggravated, and might bring the stream at upper chamber's inner structural members such as control rod guide cylinder and discharge connection place to cause vibration problem; Therefore; China build with active service nuclear power station unit than large-scale advanced pressurized water reactor unit; Power and economy still remain to be improved, and their a loop arrangement can not satisfy the security of more high-power nuclear power station one loop down layout and the requirement of economy; And external existing large nuclear power station research approach belongs to third generation moderate improvement type advanced pressurized water reactor nuclear power plant basically, and its economy and security still have the leeway of further raising.
Summary of the invention
The purpose of this invention is to provide a kind of high-power pressurized water reactor nuclear power station one circuit system structural design; It is characterized in that said high-power pressurized water reactor nuclear power station one circuit system comprises primary tank and two the two-way flow heat exchanger tube PWR steam generators with four outlets of four inlets; Adopt every two steam generators that two inlets and two outlets are arranged; The cooling-water pump of 4 reactors links to each other with four outlets of two steam generators respectively; The inlet of logical again super cooled sect trunk line of cooling-water pump and primary tank joins; And four outlets of primary tank are joined through four inlets of four hot arc trunk lines and said two steam generators respectively, thereby have guaranteed the two-way flow circulation and the heat delivered of chilled water in the circuit system.
Four inlets and four outlets of said primary tank upwards are equally distributed in the week of primary tank, and on each comfortable same surface level; The axial height at four outlet places will be lower than the axial height at four inlet places.
Said steam generator is primary side four chamber two-way flow heat exchanger tube PWR steam generators; " ten " font dividing plate is divided into four hydroeciums that cold and hot hydroecium replaces each other with hydroecium in the low head hydroecium; Connect the tube bank of inverted U pipe at low head hydroecium tube sheet upper surface, in installation cooling water inlet and the outlet corresponding of low head hydroecium bottom with hot hydroecium and cold water chamber.
Four inlets of said primary tank and the cross-sectional area of four outlets equate.
The invention has the beneficial effects as follows in the reliability of having taken all factors into consideration nuclear power station, economy; Use for reference the basis of the loop arrangement of 4 loops, 4 steam generators and AP1000; AP1000 loop under the high-power compressed water reactor nuclear power unit method of arranging more helps realizing the homogeneity in the reactor core upper chamber flow field of primary tank under 4 inlets and 4 exit conditions; And under the identical primary tank outlet total area condition, reduce the stress level at primary tank discharge connection place; Also having reduced return building materials and factory building takes up an area of.
Description of drawings
Fig. 1 is the loop arrangement rough schematic view of the first core power station AP1000 of prior art, and wherein a. is the loop arrangement rough schematic view of nuclear power station AP1000; B. be a loop arrangement rough schematic view of N4 nuclear power station.
Fig. 2 is the circuit system structural representation of primary tank four inlets, four outlets of the present invention and two steam generators.Wherein (a) is circuit system structural arrangement mode synoptic diagram; (b) be circuit system structural arrangement mode rough schematic view.
Fig. 3 is the right steam generator synoptic diagram of Fig. 2.
Fig. 4 is the left steam generator synoptic diagram of Fig. 2.
Fig. 5 is the upper chamber's velocity field under Fig. 1 scheme.
Fig. 6 is the upper chamber's velocity field under Fig. 2 scheme.
Embodiment
The present invention provides a kind of high-power pressurized water reactor nuclear power station one circuit system.Below in conjunction with embodiment and accompanying drawing thereof this present invention is further described.
Shown in Figure 2 is the circuit system structural representation of primary tank four inlets, four outlets of the present invention and two steam generators.Wherein (a) is circuit system structural arrangement mode synoptic diagram; (b) be circuit system structural arrangement mode rough schematic view.Among the figure; On upper chamber 2 positions of primary tank 1; Along being uniform-distribution with first cooling water inlet 6, second cooling water inlet 9, the 3rd cooling water inlet 13 and the 4th cooling water inlet 18 on the circumferential direction; And first coolant outlet 5, second coolant outlet 10, the 3rd coolant outlet 14 and the 4th coolant outlet 17, wherein the surface level at first cooling water inlet 6, second cooling water inlet 9, the 3rd cooling water inlet 13 and 18 places, the 4th cooling water inlet will be higher than the surface level at first coolant outlet 5, second coolant outlet 10, the 3rd coolant outlet 14 and the 4th coolant outlet 17 places of primary tank in the axial direction; First coolant outlet 5, second coolant outlet 10, the 3rd coolant outlet 14 and the 4th coolant outlet 17 link to each other with the first hot arc trunk line 7 of primary tank, the second hot arc trunk line 11, the 3rd hot arc trunk line 16, the 4th hot arc trunk line 19 respectively; The other end of the first hot arc trunk line 7, the second hot arc trunk line 11 is connected with first inlet, 22, second inlet 24 of right steam generator 4 respectively; The other end of the 3rd hot arc trunk line 16, the 4th hot arc trunk line 19 is connected with the 3rd inlet the 26, the 4th inlet 28 of left steam generator 3 respectively; One end of first cold section trunk line 8 of primary tank, secondary cooling zone trunk line 12, the 3rd cold section trunk line 15, the 4th cold section trunk line 20 links to each other with the discharge connection of first cooling-water pump 29, second cooling-water pump 30, the 3rd cooling-water pump 31, the 4th cooling-water pump 32 respectively; The inlet connection of first cooling-water pump 29, second cooling-water pump 30 links to each other with first outlet, 21, second outlet 23 of right steam generator 4 respectively, and the inlet connection of the 3rd cooling-water pump 31, the 4th cooling-water pump 32 exports 27 with the 3rd outlet the 25, the 4th of left steam generator 3 respectively and links to each other.Four inlets of above-mentioned cold section trunk line, hot arc trunk line and primary tank and the cross-sectional area of four outlets equate.
Fig. 3 is the right steam generator synoptic diagram of Fig. 2; Steam generator shown in the figure is primary side four chamber two-way flow heat exchanger tube PWR steam generators; In low head hydroecium 303, " ten " font dividing plate 316 is divided into four hydroeciums that cold and hot hydroecium replaces each other with hydroecium; Connect the inverted U pipe tube bank 307 of arranging in order at low head hydroecium 303 tube sheet upper surfaces, in installation cooling water inlet and the outlet corresponding of low head hydroecium bottom with hot hydroecium and cold water chamber.
Fig. 4 is the left steam generator synoptic diagram of Fig. 2.A left side steam generator 3 structures and right steam generator 4 structures are identical, and just the parts label changes: the inlet connection of the 3rd cooling-water pump 31, the 4th cooling-water pump 32 exports 27 with the 3rd outlet the 25, the 4th of left steam generator 3 respectively and links to each other.
When a circuit system of arranging according to the method described above moves; The chilled water of HTHP gets into the first hot arc trunk line 7, the second hot arc trunk line 11, the 3rd hot arc trunk line 16, the 4th hot arc trunk line 19 of primary tanks respectively from first coolant outlet 5 of the primary tank 1 of reactor, second coolant outlet 10, the 3rd coolant outlet 14 and the 4th coolant outlet 17; Wherein the chilled waters in the first hot arc trunk line 7, the second hot arc trunk line 11 get into chilled water first inlet 21, second inlet 23, the three hot arc trunk lines 16 of right steam generator 4, the 3rd inlet the 26, the 4th inlet 28 that the chilled waters in the 4th hot arc trunk line 19 get into left steam generator 3; The chilled water of HTHP gets into first cooling-water pump 29, second cooling-water pump 30 by first outlet, 22, second outlet 24 of right steam generator 4 respectively in left steam generator 3, right steam generator 4 after the cooling; Get into the 3rd cooling-water pump 31, the 4th cooling-water pump 32 by the 3rd outlet the 25, the 4th outlet 27 of left steam generator 3; First cooling-water pump 29, second cooling-water pump 30 pump into cooled chilled water and first cooling water inlet 6 of primary tank 1, first cold section trunk line 8, the secondary cooling zone trunk line 12 that second cooling water inlet 9 links to each other afterwards; Go forward side by side and continue circulation into primary tank 1, the 3rd cooling-water pump 31, the 4th cooling-water pump 32 also pump into cooled chilled water and get into next the circulation after the 3rd cold section trunk line 15 that link to each other with the 4th cooling water inlet 18 with the 3rd cooling water inlet 13 of primary tank 1, the 4th cold section trunk line 20 get into the chilled water that primary tanks 1 continue to be heated to be HTHP.
Fig. 5 is under the outlet total area initial physical parameter equal, chilled water the design conditions identical with total flow with Fig. 6; Velocity distribution situation in the upper chamber flow field under two kinds of contrast schemes; Contrast shows; Upper chamber of the present invention Flow Field Distribution is more even, more helps the safety of reactor core upper chamber inner structural members.
Claims (5)
1. high-power pressurized water reactor nuclear power station one a circuit system structural design is characterized in that, said high-power pressurized water reactor nuclear power station one circuit system comprises primary tank and two the two-way flow heat exchanger tube PWR steam generators with four outlets of four inlets; Adopt every two steam generators that two inlets and two outlets are arranged; The cooling-water pump of 4 reactors links to each other with four outlets of two steam generators respectively; The inlet of logical again super cooled sect trunk line of cooling-water pump and primary tank joins; And four outlets of primary tank are joined through four inlets of four hot arc trunk lines and said two steam generators respectively, thereby have guaranteed the two-way flow circulation and the heat delivered of chilled water in the circuit system.
2. according to the said a kind of high-power pressurized water reactor nuclear power station one circuit system structural design of claim 1, it is characterized in that four inlets and four outlets of said primary tank upwards are equally distributed in the week of primary tank, and on each comfortable same surface level; The axial height at four outlet places will be lower than the axial height at four inlet places.
3. according to the said a kind of high-power pressurized water reactor nuclear power station one circuit system structural design of claim 1; It is characterized in that; Said steam generator is primary side four chamber two-way flow heat exchanger tube PWR steam generators; " ten " font dividing plate is divided into cold and hot hydroecium four hydroeciums alternately each other with hydroecium in the low head hydroecium, connects the tube bank of inverted U pipe at low head hydroecium tube sheet upper surface, in installation cooling water inlet and the outlet corresponding with hot hydroecium and cold water chamber of low head hydroecium bottom.
4. according to the said a kind of high-power pressurized water reactor nuclear power station one circuit system structural design of claim 1, it is characterized in that four inlets of said primary tank and the cross-sectional area of four outlets equate.
5. according to the said a kind of high-power pressurized water reactor nuclear power station one circuit system structural design of claim 1, it is characterized in that the cross-sectional area of said cold section trunk line and hot arc trunk line equates.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2009100891306A CN101620892B (en) | 2009-07-30 | 2009-07-30 | Structural design of loop system of high-power pressurized water reactor nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2009100891306A CN101620892B (en) | 2009-07-30 | 2009-07-30 | Structural design of loop system of high-power pressurized water reactor nuclear power station |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN101620892A CN101620892A (en) | 2010-01-06 |
| CN101620892B true CN101620892B (en) | 2012-02-08 |
Family
ID=41514070
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2009100891306A Expired - Fee Related CN101620892B (en) | 2009-07-30 | 2009-07-30 | Structural design of loop system of high-power pressurized water reactor nuclear power station |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN101620892B (en) |
Families Citing this family (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101839467B (en) * | 2010-05-10 | 2012-05-16 | 中国核电工程有限公司 | Method for mounting main pipeline and main loop of pressurized water reactor nuclear power station steam generator |
| CN102324205B (en) * | 2011-08-30 | 2013-07-31 | 华北电力大学 | Experimentally runnable pressurized water reactor and steam generator simulation model thereof |
| CN104992738A (en) * | 2014-07-29 | 2015-10-21 | 台山核电合营有限公司 | Nuclear island main equipment installation process based on three-dimensional high-precision measurement |
| CN104197307B (en) * | 2014-08-25 | 2015-12-30 | 华北电力大学 | A kind of steam generator supporting clapboard structure with efficient heat transfer performance |
| CN105976877A (en) * | 2016-07-05 | 2016-09-28 | 上海核工程研究设计院 | Double-loop nuclear energy system |
| CN105913889A (en) * | 2016-07-05 | 2016-08-31 | 上海核工程研究设计院 | Three-loop nuclear energy system |
| CN106098117A (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 |
| CN106098114A (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 |
| CN106098119A (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 |
| CN106098118A (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 |
| CN106098120A (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 |
| 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 |
| CN109065193A (en) * | 2018-07-27 | 2018-12-21 | 中国核动力研究设计院 | A kind of double cooling irradiation test system and methods |
| CN110097983B (en) * | 2019-05-30 | 2023-12-08 | 华北电力大学 | External cooling three-dimensional test section of melt in-pile retention pressure vessel |
| CN110531635B (en) * | 2019-07-08 | 2020-10-23 | 华北电力大学 | Fast reactor main pump flow channel modeling calculation method based on virtual valve |
| CN111508626A (en) * | 2020-04-28 | 2020-08-07 | 中国核动力研究设计院 | Three-loop reactor coolant system suitable for ultra-large pressurized water reactor |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0232970A2 (en) * | 1986-01-10 | 1987-08-19 | Westinghouse Electric Corporation | Compact small pressurized water nuclear power plant |
| US4847038A (en) * | 1987-04-27 | 1989-07-11 | Framatome | Procedure for complete replacement of a steam generator of a pressurized water nuclear reactor |
| CN1086038A (en) * | 1992-06-24 | 1994-04-27 | 西屋电气公司 | The equipment of the hot and cold water pipeline in the nuclear force steam generating system |
| CN101351850A (en) * | 2005-11-18 | 2009-01-21 | 阿海珐核能公司 | Nuclear reactor primary circuit |
| CN101447239A (en) * | 2008-12-22 | 2009-06-03 | 中国广东核电集团有限公司 | Method for quickening drainage of circuit during overhaul period of nuclear power station |
-
2009
- 2009-07-30 CN CN2009100891306A patent/CN101620892B/en not_active Expired - Fee Related
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0232970A2 (en) * | 1986-01-10 | 1987-08-19 | Westinghouse Electric Corporation | Compact small pressurized water nuclear power plant |
| US4847038A (en) * | 1987-04-27 | 1989-07-11 | Framatome | Procedure for complete replacement of a steam generator of a pressurized water nuclear reactor |
| CN1086038A (en) * | 1992-06-24 | 1994-04-27 | 西屋电气公司 | The equipment of the hot and cold water pipeline in the nuclear force steam generating system |
| CN101351850A (en) * | 2005-11-18 | 2009-01-21 | 阿海珐核能公司 | Nuclear reactor primary circuit |
| CN101447239A (en) * | 2008-12-22 | 2009-06-03 | 中国广东核电集团有限公司 | Method for quickening drainage of circuit during overhaul period of nuclear power station |
Also Published As
| Publication number | Publication date |
|---|---|
| CN101620892A (en) | 2010-01-06 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN101620892B (en) | Structural design of loop system of high-power pressurized water reactor nuclear power station | |
| CN107293341B (en) | Pool type reactor | |
| CN101154472B (en) | Integrated low-temperature nuclear heat supplying pile | |
| CN102637465B (en) | Passive safety shell cooling system | |
| CN202615805U (en) | Non-dynamic safety case cooling system | |
| CN107492400B (en) | Dry reactor heating system | |
| CN108766592A (en) | A kind of full Natural Circulation Integrated PWR of flash distillation driving | |
| CN104575635A (en) | Accident decay heat discharge system for non-symmetric distribution of large pool type sodium-cooled fast reactors | |
| CN104089497A (en) | Heat exchange device of cooling tower | |
| CN202948739U (en) | Integrated pressurized water reactor coolant system | |
| CN206505725U (en) | Compact pressurized water reactor | |
| CN203477891U (en) | Distributed energy comprehensive utilization system for natural gas station | |
| CN102820067A (en) | Natural circulation heat exchanger for discharging waste heat of supercritical water reactor | |
| CN103531256A (en) | Pressurized water reactor prestressed concrete containment passive cooling system | |
| CN102721304A (en) | Full-serial plate shell heat exchanger | |
| CN202947336U (en) | Heat absorber of tower type solar power station | |
| CN102592688B (en) | Double-layer water rod assembly structure for supercritical water cooled reactor | |
| CN210069996U (en) | Low-temperature reactor heating system with hot water storage tank | |
| CN205388908U (en) | Ordinary pressure heat transfer system of deep well formula reactor | |
| CN201503005U (en) | Primary side four-chamber two-way flow heat exchange tube pressured water reactor steam generator | |
| CN105575449A (en) | Deep-well normal-pressure nuclear heating system | |
| CN103310856B (en) | A kind of presurized water reactor electricity generation system with inherent safety | |
| CN205334971U (en) | System for with weary pond of containment spraying system supplementary cooling | |
| CN205541975U (en) | Deep well formula ordinary pressure nuclear heating system | |
| CN210638557U (en) | A ordinary pressure heat accumulation pond for coal changes electricity |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C17 | Cessation of patent right | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20120208 Termination date: 20130730 |