CN106098114A - A kind of passive PWR nuclear power plant reactor coolant loop is arranged - Google Patents
A kind of passive PWR nuclear power plant reactor coolant loop is arranged Download PDFInfo
- Publication number
- CN106098114A CN106098114A CN201610656411.5A CN201610656411A CN106098114A CN 106098114 A CN106098114 A CN 106098114A CN 201610656411 A CN201610656411 A CN 201610656411A CN 106098114 A CN106098114 A CN 106098114A
- Authority
- CN
- China
- Prior art keywords
- steam generator
- pressure vessel
- reactor
- main
- nuclear power
- 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 49
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 22
- 238000005452 bending Methods 0.000 claims description 19
- 238000006243 chemical reaction Methods 0.000 claims description 7
- 238000005859 coupling reaction Methods 0.000 claims description 6
- 230000008676 import Effects 0.000 claims description 4
- 238000010025 steaming Methods 0.000 claims description 4
- 238000013461 design Methods 0.000 abstract description 19
- 238000004519 manufacturing process Methods 0.000 abstract description 12
- 238000005242 forging Methods 0.000 description 9
- 229910000831 Steel Inorganic materials 0.000 description 6
- 239000010959 steel Substances 0.000 description 6
- 206010016766 flatulence Diseases 0.000 description 5
- 238000000034 method Methods 0.000 description 5
- 239000004744 fabric Substances 0.000 description 4
- 239000000463 material Substances 0.000 description 4
- 238000005516 engineering process Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 230000008901 benefit Effects 0.000 description 2
- 230000008859 change Effects 0.000 description 2
- 238000010276 construction Methods 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 230000002787 reinforcement Effects 0.000 description 2
- 241000973497 Siphonognathus argyrophanes Species 0.000 description 1
- 238000003723 Smelting Methods 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 239000013078 crystal Substances 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000003754 machining Methods 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000012797 qualification Methods 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 238000007670 refining Methods 0.000 description 1
- 238000007493 shaping process Methods 0.000 description 1
- 230000000087 stabilizing effect Effects 0.000 description 1
- 239000000725 suspension Substances 0.000 description 1
- 230000008961 swelling Effects 0.000 description 1
- 238000003786 synthesis reaction Methods 0.000 description 1
- 238000009827 uniform distribution Methods 0.000 description 1
- 239000002918 waste heat 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
-
- 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
-
- 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
Abstract
The present invention provides a kind of passive PWR nuclear power plant reactor coolant loop to arrange, comprising: reactor pressure vessel；Described reactor pressure vessel has nozzle belt cylinder；Described nozzle belt cylinder is provided with reactor coolant inlet nozzle mouth and reactor coolant entrance sleeve mouth；Steam generator；Described steam generator is connected with described reactor pressure vessel by main pipeline.The passive PWR nuclear power plant reactor coolant loop that the present invention provides is arranged, reduces large-scale CAP series nuclear power plant reactor main pipe hot leg manufacture difficulty and cost, improves CAP series nuclear power plant reactor main pipe hot leg workmanship.By the design of reactor main pipe hot leg is improved, reduce the layout distance between reactor pressure vessel and steam generator, reach to reduce containment vessel radial dimension, facilitate steam generator manufacture and main system pipe arrangement, save whole Nuclear Power Station cost objective.
Description
Technical field
The present invention relates to field of pressurized water reactor nuclear, be specifically related to a kind of passive nuclear power plant reactor coolant loop cloth
Put.
Background technology
The CAP passive nuclear power station of series three generations using CAP1000 nuclear power station as representative is as China's nuclear power developing
Main way, CAP1000 nuclear power plant reactor main coolant system uses two annularly-distributed to put, and each loop respectively will reaction by one
Heap cryogen is delivered to the main pipe hot leg of steam generator and two by reactor coolant from reaction from reactor pressure vessel
Heap main coolant pump (abbreviation main pump) conveying returns cold section of the main pipeline composition of reactor pressure vessel.Each main pump entrance sleeve
Outspoken connecing is connected with steam generator outlet pressure inlet, and main pump hangs on the bottom of steam generator water chamber head.This layout
Mode eliminates connection steam generator and the reactor coolant pipe changeover portion of main pump dexterously.Meanwhile, a master is used
Pipeline hot arc and two main pipeline designs make coolant circuit pipeline in a symmetrical arrangement, at reactor main coolant loop pipeline
During flatulence of heat type, steam generator is only along main pipe hot leg direction flatulence of heat type, and beneficially steam generator cross-brace designs.But it is this
Design owing to a loop have employed a main pipe hot leg and cold section of two main pipelines so that the bore of main pipe hot leg and wall
Thick much larger than cold section of main pipeline, namely main pipe hot leg and cold section must be made up of the pipeline of two kinds of bores and wall thickness specifications.
Cause main pipe hot leg and cold section difference in manufacturing process, equipment and manufacturing technology difficulty the biggest so that main pipeline manufactures difficulty
Degree and cost are greatly increased.
Owing to main pipe hot leg caliber and wall thickness dimension are big, main pipe hot leg connecing with two forgings integrated therewith simultaneously
Ozzle, causes main pipeline forging, bends difficulty especially greatly, and main pipe hot leg is manufactured into power and qualification rate is low.
Summary of the invention
The present invention is directed to the deficiencies in the prior art, propose a kind of passive PWR nuclear power plant reactor coolant loop cloth
Put.
Passive PWR nuclear power plant reactor coolant loop is arranged, comprising:
Reactor pressure vessel；Described reactor pressure vessel has nozzle belt cylinder；Described nozzle belt cylinder is provided with instead
Answer reactor coolant discharge connection mouth and reactor coolant entrance sleeve mouth；
Steam generator；Described steam generator is connected with described reactor pressure vessel；
Main pipeline；Described main pipeline includes at least two main pipe hot legs and cold section of at least two main pipelines；Described at least
Two main pipe hot legs are arranged symmetrically with on described steam generator and reactor pressure vessel center line connecting direction；Every supervisor
Road hot arc one end coupled reaction reactor coolant discharge connection mouth, the other end connects steam generator；Described at least two main pipelines
Cold section is arranged symmetrically with on steam generator and reactor pressure vessel center line connecting direction, and cold section of one end of every main pipeline connects
Reactor coolant entrance sleeve mouth, the other end connects main pump outlet pressure inlet.
Preferably, the quantity of described steam generator is two, and is symmetricly set in the two of described reactor pressure vessel
Side.
Preferably, the water chamber head of described steam generator is arranged steam generator import mouthpiece tube in order to described master
Pipeline hot arc connects, and arranges steam generator outlet mouthpiece tube in order to be connected with described main pump.
Preferably, near the bottom of reactor pressure vessel on steam generator water chamber head, it is symmetrical arranged two and enters
Mouth pressure inlet, for connecting two main pipe hot legs；Away from the end of reactor pressure vessel on steam generator water chamber head
Portion, arranges two discharge connection mouths, for connecting two main pumps.
Preferably, on steam generator water chamber head, two entrance sleeve mouth sizes and two discharge connection mouths are symmetrical
Arrange, and on same pitch circle；Four pressure inlets arrange that with steam generator and the reactor pressure vessel line of centres be 45 ° of folders
Angle；Each pressure inlet extends downwardly from along steam generator axis direction.
Preferably, main pipe hot leg after the outside segment distance in reactor pressure vessel coolant outlet nozzle mouth direction,
Being 3-6 times of caliber by a bending radius, angle of bend is that the bend pipe of 20 °～40 ° turns to steam generator in horizontal plane
Pressure inlet direction, is then 1.5～2.5 times of calibers by a bending radius, and angle of bend is that 90 ° of bend pipes are upwards sent out with steam
Raw device entrance sleeve mouth connects.
Preferably, cold section of main pipeline is after the distance of outside one end, main pump outlet pressure inlet direction, by a bending radius
For 70 °～90 ° of bend pipe steering reaction core pressure vessel coolant inlet pressure inlet directions in horizontal plane of 3-5 times of caliber, with
Reactor pressure vessel coolant inlet pressure inlet connects.
Compared with prior art, the method have the advantages that
1, the passive PWR nuclear power plant reactor coolant loop that the present invention provides is arranged, reduces large-scale CAP series
Nuclear power plant reactor main pipe hot leg manufacture difficulty and cost, improve CAP series nuclear power plant reactor main pipe hot leg and manufacture matter
Amount.By the design of reactor main pipe hot leg is improved, reduce the layout between reactor pressure vessel and steam generator
Distance, reaches to reduce containment vessel radial dimension, facilitates steam generator manufacture and main system pipe arrangement, save whole
Nuclear Power Station cost objective.
2, the passive PWR nuclear power plant reactor coolant loop that the present invention provides is arranged, relative to same power
The CAP series nuclear power station of two traditional loops, has a following technical characterstic:
1) main pipeline manufacture view
A) divide into two main pipe hot legs due to a main pipe hot leg.Main pipe hot leg caliber size reduces, and is used for
The steel ingot or the electroslag remelting steel ingot that manufacture a main pipe hot leg reduce more than 30%.The smelting of main pipe hot leg material can be reduced
Refining equipment, can reduce forging press tonnage, can reduce machining apparatus size, reduces Equipment for Heating Processing ability need, because of
This is conducive to the manufacture of main pipe hot leg.
B) reduce due to main pipe hot leg caliber size, beneficially main pipe hot leg forging so that main pipeline blank can
Forging thoroughly, reaches material grains degree purpose by forging, improves main pipeline workmanship；Advantageously reduce main pipe hot leg to forge back
Stove adds showing tremendous enthusiasm time, prevents crystal grain from swelling, and improves material grains degree.
C) reduce due to main pipe hot leg bore and wall thickness dimension, and bigger bending radius can be designed to, favorably
Bend the ability need of power-equipment in reduction main pipeline, be conducive to reducing bending mould size, beneficially main pipe hot leg curved
Dimension control processed, beneficially main pipe hot leg bend and measure.
D) reduce due to main pipe hot leg bore and wall thickness dimension, effectively in improve main pipe hot leg solution treatment effect and
Control main pipeline solution treatment deformation.
E) have only to arrange the pressure inlet of a forging integrated therewith, beneficially main pipeline forging due to every main pipe hot leg
Make；Be conducive to the design of main pipeline bending mould；Be conducive to will take over mouth and be away from pipe bending position, be greatly reduced pressure inlet pair
The impact of metal flow, facilitates metal flow during pipe bending, and strong and main pipe hot leg bends shaping and size Control.
2) Factory Building layout aspect
A) reduce due to main pipe hot leg bore, be conducive to reducing hot segment of bent pipe of main pipeline space, it is thus possible to reduce and steam
Vapour generator, to the distance between reactor pressure vessel, reaches to reduce the radial dimension of steel containment vessel of nuclear power station, has
It is beneficial to reduce design difficulty and the construction cost of steel containment vessel of nuclear power station.
B) only arranging, due to every main pipe hot leg, the pressure inlet that a forging integrated therewith connects, beneficially pressure inlet exists
Layout design on main pipe hot leg, convenient adapter pipe arrangement, such as the pipe arrangement of fourth stage ADS system.It is thus able to subtract
Little main system pipe arrangement, to reactor building space requirement, reaches to reduce the radial dimension of steel containment vessel of nuclear power station, favorably
In the design difficulty and the construction cost that reduce steel containment vessel of nuclear power station.
C) it is arranged in both sides rather than the centre of steam generator line due to main pipe hot leg, main pipe hot leg relative
Length increases.The arrangement space of putting making main pipe hot leg upper connecting tube mouth increases, beneficially surge ozzle, Residual heat removal pipe
Pressure inlet and fourth stage ADS pressure inlet are arranged.
D) owing to surge nozzle set is on main pipe hot leg horizontal segment position, the ripple on main pipe hot leg is reduced
Dynamic pipe pressure inlet position, the beneficially layout design of Surge line piping, reach to prevent Surge line piping thermally stratified layer effect.Voltage stabilizing can also be reduced
Requirement for height arranged by device, advantageously reduces first and second and three grades of ADS pipeline seismic forces at manostat top.
E) owing to maintaining reactor main cooling system two loop layout, be conducive to reducing containment vessel size, have
It is beneficial to save Nuclear Power Station cost.
F) owing to maintaining reactor main cooling system two loop layout, and each loop is to be arranged symmetrically with, and steam is sent out
Raw device is only along toward steam generator and reactor pressure vessel line direction flatulence of heat type, and beneficially steam generator cross-brace sets
Meter.
3) steam generator aspect
A) owing to having two entrance sleeve mouths and two discharge connection mouths on each steam generator water chamber head, their chi
Very little identical with structure, and full symmetric layout on same pitch circle, the beneficially design of steam generator water chamber head and
Manufacture.
B) owing to being provided with the entrance sleeve mouth of two reduced sizes on each steam generator water chamber head, pressure inlet
Bore size reduces, beneficially steam generator entrance sleeve mouth reinforcement for openings design.
4) main pipeline installation
A) it is to arrange in horizontal and vertical plane respectively due to two continuous bend pipes on main pipe hot leg, is conducive to main
Pipe bending angle, bending radius are measured.
B) owing to have employed two main pipe hot legs, main pipe hot leg bore and wall thickness dimension reduce, and main pipeline is warm
Section has two bending sections, beneficially main pipe hot leg absorption system flatulence of heat type stress and main pipeline mount stress.
C) owing to have employed two main pipe hot legs, main pipe hot leg and cold section of main pipeline can be designed to same diameter and
Wall thickness, is conducive to system flatulence of heat type stress and main pipeline mount stress uniform distribution, thus reduces main pipeline stress.
D) it is arranged in both sides rather than the centre of steam generator line due to main pipe hot leg, and main pipe hot leg and steaming
Vapour generator entrance sleeve mouth (see part 7) connects in horizontal plane, and cold section of main pipeline and main pump outlet pressure inlet (see part 11) exist
Connecting in vertical plane, beneficially main pipe hot leg and cold section of main pipeline is installed boil on the nape opposite the mouth adjustment and measures.
E) it is to arrange in horizontal and vertical plane respectively due to two continuous bend pipes on main pipe hot leg, is conducive to main
Pipe bending angle, bending radius are measured.
Accompanying drawing explanation
Fig. 1 be meet the preferred embodiment of the present invention passive PWR nuclear power plant reactor coolant loop arrange bow
View.
Fig. 2 is to meet the side that the passive PWR nuclear power plant reactor coolant loop of the preferred embodiment of the present invention is arranged
View.
In figure, 1 reactor pressure vessel nozzle belt cylinder, 2 reactor coolant entrance sleeve mouths, 3
Reactor coolant inlet nozzle mouth, cold section of A of 4 main pipelines, 5 main pipe hot leg A, 6 surge ozzles,
7 steam generator entrance sleeve mouths, 8 steam generator water chamber heads, 9 steam generator outlet pressure inlets,
10 main pumps, 11 main pump outlet pressure inlets, 12 fourth stage ADS pressure inlets, 13 main pipe hot leg B,
Cold section of B of 14 main pipelines, 15 fourth stage ADS pressure inlets, 16 main pipe hot leg C, 17 Residual heat removal adapters
Mouth, 18 fourth stage ADS pressure inlets, 19 main pipe hot leg D, cold section of D of 20 main pipelines, 21 steam generations
Device, 22 steam generator vertical support, 23 reactor pressure vessels, 24 steam generator lower, transverse are propped up
Support.
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 illustrated in fig. 1 and 2, arrange for passive PWR nuclear power plant reactor coolant loop, including:
1. reactor pressure vessel:
Under conditions of reactor pressure vessel nozzle belt cylinder (see part 1) perforate allows, connect at reactor pressure vessel
Pipeline section cylinder arranges four reactor coolant inlet nozzle mouths (see part 3), for connecting four main pipe hot legs (see part 5, part
13, part 16 and part 19), and four reactor coolant entrance sleeve mouths are set, for connect cold section of four main pipelines (see part 4,
Part 14, part 15 and part 20).Four reactor coolant inlet nozzle mouths are arranged symmetrically with, with steam generator (see part 21) and anti-
Answering pressure container (see part 23) line is certain angle, along radially outward stretching at reactor pressure vessel nozzle belt cylinder
Go out.Four reactor coolant entrance sleeve mouths are also arranged symmetrically with, and hold with steam generator (see part 21) and reactor pressure
Device (see part 23) line, also in certain angle, extends radially out along reactor pressure vessel nozzle belt cylinder.
At reactor pressure vessel nozzle belt cylinder circumference, four reactor coolant inlet nozzle mouths and entrance sleeve mouth
Under conditions of reinforcement for openings allows, should be close proximity to.Axial at reactor pressure vessel, four reactor coolant outlets connect
Ozzle and the discrepancy in elevation up and down of entrance sleeve mouth, should be designed by main system technique and reactor pressure vessel and determine.
2. steam generator:
On steam generator water chamber head (see part 8), with steam generator (see part 21) and reactor pressure vessel (see
Part 23) line is axis of symmetry, is symmetrical arranged two entrance sleeve mouths (see part 7), for connect two main pipe hot legs (see part 5,
Part 13 or see part 16 and part 19).On steam generator water chamber head (see part 8), be also symmetrical arranged two discharge connection mouths (see
Part 9), for connecting two main pumps (see part 10).Two entrance sleeve mouths on steam generator water chamber head and two outlets
The full symmetric layout of pressure inlet, and on same pitch circle.Four pressure inlets are arranged and steam generator and reactor pressure vessel
The line of centres is 45 ° of angles.Two are entered pressure inlet and two discharge connection mouths may be designed to structure and equivalently-sized, all along steam
Generator axis direction extends downwardly from.
On steam generator water chamber head, two entrance sleeve mouths and two discharge connection mouth pitch diameters, be according to reaction
Heap pressure holds the distance between steam generator, reactor pressure vessel upper outlet and entrance sleeve mouth angle, main pipeline heat
Section and the angle of bend of cold section and bending radius, and steam generator water chamber head design synthesis determines.Steam generator water
On the end socket of room two entrance sleeve mouths and two discharge connection mouth pitch diameters also with two main pump sizes, steam generator is vertical
Support relevant with steam generator lower, transverse supported design.
3. main pipeline:
Main pipe hot leg (see part 5, part 13, part 16, part 19) and cold section of main pipeline (see part 4, part 14, part 15, part 20)
Bore and wall thickness dimension should be designed to identical or essentially identical, are so conducive to main pipe hot leg and the manufacture of cold section.Each cold
But two main pipe hot legs (see part 5, part 13 or see part 16, part 19) of agent loop are at reactor pressure vessel and steam generator
Being arranged symmetrically with on two line directions, every main pipe hot leg one end coupled reaction core pressure vessel discharge connection mouth, the other end connects
Steam generator entrance sleeve mouth.Main pipe hot leg after the outside segment distance in reactor pressure vessel discharge connection mouth direction,
Being 3-6 times of caliber by a bending radius, angle of bend is that the bend pipe of 20 °～40 ° turns to steam generator in horizontal plane
Pressure inlet direction, is then 1.5～2.5 times of calibers by a bending radius, and angle of bend is that 90 ° of bend pipes are upwards sent out with steam
Raw device entrance sleeve mouth vertically connects.The bend pipe of every main pipe hot leg is overall Curved Continuous pipeline, and 90 ° of bend pipe ends can be according to master
Equipment and main pipeline are arranged to be needed to determine arrange or be not provided with straight section.
Every main pipe hot leg only arranges the pressure inlet of a bigbore connection integrated therewith, and these pressure inlets are respectively
Surge ozzle (see part 6), waste heat send pressure inlet (see part 17) and two fourth stage ADS (automatically unloading system) pressure inlets
(see part 12 and part 18).These pressure inlets can be arranged according to main system design and Factory Building it needs to be determined that be specifically located at that root supervisor
On road hot arc.
In addition to the spigot joint Three-dimensional cloth of Surge line piping is put, remaining pressure inlet is all arranged vertically.Adapter on every main pipe hot leg
Mouth should be tried one's best more than bend pipe inflection point distance 100mm, to reduce the flowing of material when pressure inlet stops bend pipe.Every supervisor
Pressure inlet edge on road hot arc is more than primary shielding metope distance 300mm, to facilitate adapter welding and inservice inspection.Supervisor
Surge line piping on road hot arc is spigot joint, is arranged in main pipe hot leg horizontal straight tube section, advantageously ensures that Surge line piping has enough slopes
Degree prevents thermally stratified layer.Also contribute to manostat simultaneously and can be arranged to the lowest, to reduce manostat and its top duct
Seismic force.It is also relevant with main system adapter layout that pressure inlet on main pipe hot leg arranges layout.
Cold section of two main pipelines of each coolant loop (see part 4, part 14 or see part 15, part 20) are at reactor and steam
Generator line is arranged symmetrically with on direction, cold section of one end coupled reaction core pressure vessel entrance sleeve mouth of every main pipeline, another
End connects main pump outlet pressure inlet.Cold section of main pipeline is after the distance of outside one end, main pump outlet pressure inlet direction, curved by one
Bilge radius be the angle of bend of 3-5 times of caliber be the bend pipe of 70 °～90 ° steering reaction core pressure vessel pressure inlet in horizontal plane
Direction, is connected with reactor pressure vessel entrance sleeve mouth.Cold section of bend pipe of every main pipeline is overall bend pipe.
4. major loop is arranged:
The reactor main coolant loop of the present invention is two loops, and two loops are arranged symmetrically with.Each loop is by two masters
Pipeline hot arc, cold section, one steam generator of two main pipelines and two group pump compositions.Two main pipe hot leg one end connect respectively
Connecing two discharge connection mouths of reactor pressure vessel, the other end connects two entrance sleeve mouths of steam generator respectively.Two masters
The entrance sleeve mouth of pump is connected with two discharge connection mouths of steam generator respectively, and main pump connects suspension by its entrance sleeve is outspoken
In steam generator water chamber head bottom.Cold section of one end of two main pipelines connects two main pump outlet pressure inlets, the other end respectively
Two entrance sleeve mouths of coupled reaction core pressure vessel respectively.
Each two main pipe hot legs of reactor Main Coolant loop, cold section and two main pumps of two main pipelines are sent out with steam
Raw device and reactor pressure vessel line are arranged symmetrically.Wherein main pipe hot leg is arranged in inside loop, cold section of cloth of main pipeline
Put outside loop.
Meeting, reactor pressure vessel adapter cylinder section imports and exports pressure inlet design, steam generator water chamber head sets
Meter, the design of steam generator supported design, main pipe hot leg and the condition of cold section of main pipeline design, steam generator is to reaction pressure
The distance of force container should be tried one's best closely.To shorten main pipe hot leg and the length of cold section, thus containment vessel can be reduced
Diameter dimension, beneficially Nuclear Power Station cost reduce.
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 (7)
1. a passive PWR nuclear power plant reactor coolant loop is arranged, it is characterised in that including:
Reactor pressure vessel；Described reactor pressure vessel has nozzle belt cylinder；Described nozzle belt cylinder is provided with reactor
Coolant outlet nozzle mouth and reactor coolant entrance sleeve mouth；
Steam generator；Described steam generator is connected with described reactor pressure vessel；
Main pipeline；Described main pipeline includes at least two main pipe hot legs and cold section of at least two main pipelines；Described at least two
Main pipe hot leg is arranged symmetrically with on described steam generator and reactor pressure vessel center line connecting direction；Every main pipeline heat
Duan Yiduan coupled reaction core pressure vessel discharge connection mouth, the other end connects steam generator entrance sleeve mouth；Described at least two
Cold section of root main pipeline is arranged symmetrically with on steam generator and reactor pressure vessel center line connecting direction, cold section of every main pipeline
One end coupled reaction core pressure vessel entrance sleeve mouth, the other end connects main pump outlet pressure inlet.
2. passive PWR nuclear power plant reactor coolant loop as claimed in claim 1 is arranged, it is characterised in that described
The quantity of steam generator is two, and is symmetricly set in the both sides of described reactor pressure vessel.
3. passive PWR nuclear power plant reactor coolant loop as claimed in claim 1 is arranged, it is characterised in that described
Steam generator import mouthpiece tube is set on the water chamber head of steam generator in order to be connected with described main pipe hot leg, steaming is set
Vapour generator outlet mouthpiece tube is in order to be connected with described main pump.
4. passive PWR nuclear power plant reactor coolant loop as claimed in claim 3 is arranged, it is characterised in that steaming
Near the side of reactor pressure vessel on vapour generator water chamber head, it is symmetrical arranged two entrance sleeve mouths, for connection two
Root main pipe hot leg；Away from the bottom of reactor pressure vessel on steam generator water chamber head, two discharge connections are set
Mouth, for connecting two main pumps.
5. passive PWR nuclear power plant reactor coolant loop as claimed in claim 4 is arranged, it is characterised in that steam
On generator water chamber head, two entrance sleeve mouth sizes and two discharge connection mouths are arranged symmetrically, and at same pitch circle
On；Four pressure inlets arrange that with steam generator and the reactor pressure vessel line of centres be 45 ° of angles；Each pressure inlet is along steaming
Vapour generator axis direction extends downwardly from.
6. passive PWR nuclear power plant reactor coolant loop as claimed in claim 1 is arranged, it is characterised in that supervisor
Road hot arc, after the outside segment distance in reactor pressure vessel coolant outlet nozzle mouth direction, is 3-by a bending radius
6 times of calibers, angle of bend is that the bend pipe of 20 °～40 ° turns to steam generator pressure inlet direction, then by one in horizontal plane
Individual bending radius is 1.5～2.5 times of calibers, and angle of bend is that 90 ° of bend pipes are upwards connected with steam generator entrance sleeve mouth.
7. passive PWR nuclear power plant reactor coolant loop as claimed in claim 1 is arranged, it is characterised in that supervisor
Cold section of road after the distance of outside one end, main pump outlet pressure inlet direction, by bending radius is 3-5 times of caliber 70 °～
90 ° of bend pipe steering reaction core pressure vessel coolant inlet pressure inlet directions in horizontal plane, with reactor pressure vessel import
Pressure inlet connects.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610656411.5A CN106098114A (en) | 2016-08-11 | 2016-08-11 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610656411.5A CN106098114A (en) | 2016-08-11 | 2016-08-11 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN106098114A true CN106098114A (en) | 2016-11-09 |
Family
ID=57456227
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610656411.5A Pending CN106098114A (en) | 2016-08-11 | 2016-08-11 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN106098114A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108257684A (en) * | 2017-12-28 | 2018-07-06 | 中广核研究院有限公司 | Reactor pressure vessel and its method of work |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101620892A (en) * | 2009-07-30 | 2010-01-06 | 华北电力大学 | Structural design of loop system of high-power pressurized water reactor nuclear power station |
| CN101839467A (en) * | 2010-05-10 | 2010-09-22 | 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 |
| CN102169736A (en) * | 2011-01-19 | 2011-08-31 | 中国核工业第五建设有限公司 | Installing method for main pipeline of coolant system of nuclear power station |
| CN103769723A (en) * | 2013-12-31 | 2014-05-07 | 浙江省火电建设公司 | Nuclear island primary coolant circuit main pipe installation method |
| WO2015061641A1 (en) * | 2013-10-24 | 2015-04-30 | Holtec International | Steam generator for nuclear steam supply system |
| KR20160081081A (en) * | 2014-12-30 | 2016-07-08 | 한국원자력연구원 | Modular nuclear reactor and nuclear power plant having the same |
| CN105810256A (en) * | 2014-12-29 | 2016-07-27 | 国核华清（北京）核电技术研发中心有限公司 | Passive residual heat removal system for nuclear power plant |
-
2016
- 2016-08-11 CN CN201610656411.5A patent/CN106098114A/en active Pending
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101620892A (en) * | 2009-07-30 | 2010-01-06 | 华北电力大学 | Structural design of loop system of high-power pressurized water reactor nuclear power station |
| CN101839467A (en) * | 2010-05-10 | 2010-09-22 | 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 |
| CN102169736A (en) * | 2011-01-19 | 2011-08-31 | 中国核工业第五建设有限公司 | Installing method for main pipeline of coolant system of nuclear power station |
| WO2015061641A1 (en) * | 2013-10-24 | 2015-04-30 | Holtec International | Steam generator for nuclear steam supply system |
| CN103769723A (en) * | 2013-12-31 | 2014-05-07 | 浙江省火电建设公司 | Nuclear island primary coolant circuit main pipe installation method |
| CN105810256A (en) * | 2014-12-29 | 2016-07-27 | 国核华清（北京）核电技术研发中心有限公司 | Passive residual heat removal system for nuclear power plant |
| KR20160081081A (en) * | 2014-12-30 | 2016-07-08 | 한국원자력연구원 | Modular nuclear reactor and nuclear power plant having the same |
Non-Patent Citations (2)
| Title |
|---|
| 夏栓;徐臻;: "AP1000冷却剂回路主管道流场分析" * |
| 左学兵;陈晶晶;张金东;代帅;郑东宏;: "AP1000反应堆冷却剂系统主要设备安装技术" * |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108257684A (en) * | 2017-12-28 | 2018-07-06 | 中广核研究院有限公司 | Reactor pressure vessel and its method of work |
| CN108257684B (en) * | 2017-12-28 | 2023-10-31 | 中广核研究院有限公司 | Reactor pressure vessel and method for operating the same |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN106098115A (en) | A kind of passive PWR nuclear power plant reactor coolant loop is arranged | |
| CN106098116A (en) | A kind of passive PWR nuclear power plant reactor coolant loop is arranged | |
| CN106282517A (en) | The heat treatment deformation frock of Thin Wall Cylinder Blocks foundry goods and heat treatment shove charge method thereof | |
| CN107252866A (en) | The multiple protrusion ozzle large-sized end enclosure forging integral forging and forming methods of nuclear reactor band | |
| CN104439972B (en) | A kind of mammoth conveter is deducted marks two lobe preparation methods | |
| CN106098114A (en) | A kind of passive PWR nuclear power plant reactor coolant loop is arranged | |
| CN103542214B (en) | Heavy caliber high-strength pipe-line hot drawing threeway wall thickness computational methods | |
| CN106098119A (en) | A kind of passive PWR nuclear power plant reactor coolant loop is arranged | |
| CN106098118A (en) | A kind of passive PWR nuclear power plant reactor coolant loop is arranged | |
| CN106098120A (en) | A kind of passive PWR nuclear power plant reactor coolant loop is arranged | |
| CN110116183A (en) | A kind of flange forging molding die and forging method | |
| CN106098117A (en) | A kind of passive PWR nuclear power plant reactor coolant loop is arranged | |
| CN213761307U (en) | Pipeline vapour-liquid mixing generator | |
| CN108509758A (en) | The computational methods of ditch allowable stress under a kind of oil-gas pipeline | |
| CN205535770U (en) | Lower sediment device of circulating fluidized bed boiler | |
| CN205784619U (en) | A kind of water-cooled hanging arm roll for billet heating furnace | |
| CN208466920U (en) | A kind of mid-frequency induction heating push-making angle fitting device | |
| CN209109142U (en) | A kind of water-tube reaction unit with independent cooler tube bundle | |
| CN202582208U (en) | Long-life flow-equalizing type high-temperature discharging device | |
| CN219518779U (en) | Loop reactor | |
| CN206943657U (en) | A kind of metal three-way pipe of hot extrusion molding | |
| CN208644531U (en) | A kind of conduit stack mounted welder | |
| CN209144192U (en) | Oxygen top-blown converter is used in a kind of production of Hi-Stren steel | |
| CN209205319U (en) | A kind of resin transfer device for mixed ion exchanger | |
| CN112121658A (en) | Pipeline vapour-liquid mixing generator |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| 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 |