CN106098118A - 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
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- CN106098118A CN106098118A CN201610657281.7A CN201610657281A CN106098118A CN 106098118 A CN106098118 A CN 106098118A CN 201610657281 A CN201610657281 A CN 201610657281A CN 106098118 A CN106098118 A CN 106098118A
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- 238000005452 bending Methods 0.000 claims description 13
- 238000005242 forging Methods 0.000 claims description 12
- 238000005859 coupling reaction Methods 0.000 claims description 7
- 238000006243 chemical reaction Methods 0.000 claims description 6
- 239000007787 solid Substances 0.000 claims description 5
- 239000002918 waste heat Substances 0.000 claims description 2
- 238000013461 design Methods 0.000 abstract description 21
- 238000004519 manufacturing process Methods 0.000 abstract description 10
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 16
- 229910000831 Steel Inorganic materials 0.000 description 6
- 239000004744 fabric Substances 0.000 description 6
- 238000000034 method Methods 0.000 description 6
- 239000010959 steel Substances 0.000 description 6
- 206010016766 flatulence Diseases 0.000 description 5
- 239000000463 material Substances 0.000 description 4
- 230000009286 beneficial effect Effects 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000008901 benefit Effects 0.000 description 2
- 230000015572 biosynthetic process 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
- 230000008676 import Effects 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 230000002787 reinforcement Effects 0.000 description 2
- 238000003786 synthesis reaction Methods 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
- 239000003795 chemical substances by application Substances 0.000 description 1
- 239000013078 crystal Substances 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- PCHJSUWPFVWCPO-UHFFFAOYSA-N gold Chemical compound [Au] PCHJSUWPFVWCPO-UHFFFAOYSA-N 0.000 description 1
- 239000010931 gold Substances 0.000 description 1
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- 229910052751 metal Inorganic materials 0.000 description 1
- 230000002265 prevention Effects 0.000 description 1
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Classifications
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- 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
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- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
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 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 is with the adapter of two solid forgings simultaneously
Mouth, 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 cloth includes:
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 cold section of at least two main pipelines and at least two main pipe hot legs；Described at least
Cold section of two main pipelines are arranged symmetrically in the both sides of steam generator and reactor pressure vessel line, for coupled reaction heap pressure
Force container coolant inlet pressure inlet and main pump outlet pressure inlet；Described at least two main pipe hot legs are arranged symmetrically in steam and send out
Raw device and the both sides of reactor pressure vessel line, and it is positioned at the inner side of cold section of described main pipeline, for coupled reaction heap pressure
Container coolant outlet nozzle mouth and steam generator entrance sleeve mouth.
Preferably, the quantity of described steam generator is two, and is symmetricly set in the two of described reactor pressure vessel
Side, each steam generator is connected with reactor pressure vessel by two main pipe hot legs.
Preferably, each steam generator is provided with two main pumps, and reactor pressure vessel is by cold section an of main pipeline
It is connected with one of them main pump.
Preferably, every main pipe hot leg only arranges a bigbore pressure inlet being connected with supervisor's solid forging, this
A little pressure inlet respectively surge ozzles, waste heat send pressure inlet and two fourth stage ADS pressure inlets.
Preferably, steam generator is provided with two entrance sleeve mouths and connects in order to connect two main pipe hot legs and two outlets
Ozzle is in order to connect two main pumps.
Preferably, cold section of described main pipeline is after the distance of outside one end, main pump outlet pressure inlet direction, by a bending
Radius is 70 °～cold section of bend pipe of 90 ° of main pipelines steering reaction core pressure vessel pressure inlet side in horizontal plane of 3-5 times of caliber
To, it is connected with reactor pressure vessel entrance sleeve mouth.
Preferably, cold section of bend pipe of described main pipeline is overall bend pipe.
Preferably, described main pipe hot leg, after the outside segment distance in reactor coolant inlet nozzle mouth direction, passes through
One bending radius is 1.5-3 times of caliber, and angle of bend is that the hot segment of bent pipe of main pipeline of 30 °～60 ° turns in 3 D plane
Steam generator pressure inlet radial direction, is connected with steam generator entrance sleeve mouth.
Preferably, described hot segment of bent pipe of main pipeline is overall bend pipe.
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 main system pipe arrangement, save whole Nuclear Power Station cost mesh
Mark.
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, and relatively
Little angle of bend, advantageously reduces main pipeline and bends the ability need of power-equipment, is conducive to reducing bending mould size, has
Being beneficial to main pipe hot leg and bend dimension control, beneficially main pipe hot leg bends and measures.
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) forge owing to every main pipe hot leg has only to arrange the pressure inlet of a solid forging, beneficially main pipeline,
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 to gold
Belong to the impact of flowing, facilitate metal flow during pipe bending, beneficially main pipe hot leg to bend 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, and cloth in 3 D plane due to main pipe hot leg
Putting, the straight length relative length of main pipe hot leg increases.Make main pipe hot leg upper connecting tube mouth put arrangement space to increase, be conducive to
Surge ozzle, Residual heat removal pipe pressure inlet and fourth stage ADS pressure inlet are arranged.
D) due to can be by surge nozzle set on the horizontal pipeline section of main pipe hot leg, it is possible to decrease on main pipe hot leg
Surge ozzle position, the beneficially layout design of Surge line piping, reach to prevent Surge line piping thermally stratified layer effect.Can also reduce
Manostat arranges requirement for height, 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, and in being arranged symmetrically with two-by-two, the beneficially design of steam generator water chamber head and manufacture.
B) it is provided with the entrance sleeve mouth of two reduced sizes, opening of pressure inlet due to each steam generator water chamber head
Hole dimension reduces, beneficially steam generator entrance sleeve mouth reinforcement for openings design.
4) main pipeline installation
A) longer due to the straight section at hot segment of bent pipe of main pipeline two ends, beneficially main pipeline angle of bend, bending radius is 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 bends in 3 D plane, and the straight section at hot segment of bent pipe of main pipeline two ends is longer, 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, and cloth in 3 D plane due to main pipe hot leg
Put so that main pipe hot leg horizontal segment gradient method of adjustment is more flexible, beneficially main pipe hot leg boil on the nape opposite the mouth.
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 sections 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 main pipe hot leg B, 13 the 4th sections of ADS pressure inlets,
Cold section of B of 14 main pipelines, cold section of C of 15 main pipelines, 16 main pipe hot leg C, 17 main pipeline Residual heat removal connect
Ozzle, main pipe hot leg D, 19 the 4th sections of ADS pressure inlets, cold section of D of 20 main pipelines, 21 steam generators,
22 steam generator vertical support, 23 reactor pressure vessels, 24 steam generator lower, transverse 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
12, part 16 and part 18), 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), near the side of reactor pressure vessel (see part 23), with steam
Generator (see part 21) and reactor pressure vessel line are axis of symmetry, are symmetrical arranged two entrance sleeve mouths (see part 7), are used for
Connect two main pipe hot legs (see part 5, part 12 or see part 16, part 18).Being set to of two entrance sleeve mouths is square obliquely downwards
To setting, and it is certain angle with steam generator and reactor pressure vessel line vertical plane.Two entrance sleeve mouths
Radially stretch out obliquely downwards along steam generator water chamber head spheroid, be connected obliquely downwards with two main pipe hot legs.
On steam generator water chamber head, away from the bottom of reactor pressure vessel, with steam generator and reactor
Pressure vessel line is axis of symmetry, is symmetrical arranged two discharge connection mouths (see part 9), for connecting two main pumps (see part 10).
On steam generator water chamber head, two discharge connection mouths axially downwardly stretch out along steam generator, downward with two main pumps
Connect.
The concrete angle in horizontal and vertical plane of two the entrance sleeve mouths on steam generator water chamber head, root
The distance between steam generator, two discharge connection mouth angles on reactor pressure vessel, supervisor is held according to reactor pressure
Road hot arc angle of bend and bending radius, the design of steam generator water chamber head and steam generator vertical support are (see part
22) design synthesis determines.
The distance between two discharge connection mouths on steam generator water chamber head and from steam generator center away from
From, the distance between steam generator to be held according to reactor pressure, two entrance sleeve mouth folders on reactor pressure vessel
Angle, cold section of angle of bend of main pipeline and bending radius, the design of steam generator water chamber head and two main pumps (see part 10)
Size, steam generator vertical support design synthesis determines.
3. main pipeline:
Main pipe hot leg (see part 5, part 12, part 16, part 18) 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 12 or see part 16, part 18) of agent loop are in reactor and steam generator two line direction
On be arranged symmetrically with.Every main pipe hot leg one end coupled reaction core pressure vessel discharge connection mouth, the other end connects steam generation
Device entrance sleeve mouth.Main pipe hot leg is after the outside segment distance in reactor pressure vessel discharge connection mouth direction, by one
Bending radius is 1.5-3 times of caliber, and angle of bend is that the bend pipe of 30 °～60 ° turns to steam generator pressure inlet in three-dimensional surface
Radial direction, and be connected with steam generator entrance sleeve mouth.The bend pipe of every main pipe hot leg is overall bend pipe.
Every main pipe hot leg only arranges a bigbore pressure inlet with main pipeline solid forging, and these pressure inlets divide
Wei surge ozzle (see part 6), Residual heat removal pressure inlet (see part 17) and two fourth stage ADS (automatically unloading system) not connect
Ozzle (see part 13 and part 19).These pressure inlets can be arranged it needs to be determined that be specifically located at that root according to main system design and Factory Building
On main pipe hot leg.
May be arranged on the straight length being connected with steam generator except Surge line piping is spigot joint, and outside three-dimensional layout, remaining connects
Ozzle is arranged on the straight length that main pipe hot leg is connected with reactor pressure vessel, and is arranged vertically.Every main pipeline heat
Pressure inlet in section should be tried one's best more than bend pipe inflection point distance 100mm, to reduce the flowing of pressure inlet prevention pipe material.Often
Pressure inlet edge on root main pipe hot leg is more than primary shielding metope distance 300mm, to facilitate adapter welding and in-service inspection
Look into.Surge line piping on main pipe hot leg is spigot joint if able to be arranged on horizontal pipeline section, should be arranged on horizontal pipeline section as far as possible.As
Really Surge line piping is spigot joint can only be arranged on the straight length being connected with steam generator import, and the spigot joint position of Surge line piping should be tried one's best
Low, to ensure that Surge line piping has enough gradients to prevent thermally stratified layer.Also contribute to manostat simultaneously and can be arranged to the lowest, with
Reduce the seismic force of manostat and its top duct.Pressure inlet on main pipe hot leg arranges layout and also arranges with main system adapter
Relevant.
Cold section of two main pipelines of each coolant loop (see part 4, part 14 or see part 16, part 20) are at reactor and steam
Generator two 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 is 3-5 times of caliber, and angle of bend is 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 two 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 (9)
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 cold section of at least two main pipelines and at least two main pipe hot legs；Described at least two
Cold section of main pipeline is arranged symmetrically in the both sides of steam generator and reactor pressure vessel line, holds for coupled reaction heap pressure
Device coolant inlet pressure inlet and main pump outlet pressure inlet；Described at least two main pipe hot legs are arranged symmetrically in steam generator
With the both sides of reactor pressure vessel line, and it is positioned at the inner side of cold section of described main pipeline, for coupled reaction core pressure vessel
Coolant outlet nozzle mouth and steam generator entrance sleeve mouth.
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, and each steam generator leads to
Cross two main pipe hot legs to be connected with reactor pressure vessel.
3. passive PWR nuclear power plant reactor coolant loop as claimed in claim 1 is arranged, it is characterised in that each
Steam generator is provided with two main pumps, and reactor pressure vessel is connected with one of them main pump by cold section an of main pipeline.
4. passive PWR nuclear power plant reactor coolant loop as claimed in claim 1 is arranged, it is characterised in that every
Main pipe hot leg only arranges a bigbore pressure inlet being connected with supervisor's solid forging, and these pressure inlets are respectively Surge line piping
Pressure inlet, waste heat send pressure inlet and two fourth stage ADS pressure inlets.
5. passive PWR nuclear power plant reactor coolant loop as claimed in claim 1 is arranged, it is characterised in that steam
Generator is provided with two entrance sleeve mouths in order to connect two main pipe hot legs and two discharge connection mouths in order to connect two masters
Cold section of pipeline.
6. passive PWR nuclear power plant reactor coolant loop as claimed in claim 1 is arranged, it is characterised in that described
Cold section of main pipeline is after the distance of outside one end, main pump outlet pressure inlet direction, by 70 ° that bending radius is 3-5 times of caliber
～cold section of bend pipe of 90 ° of main pipelines steering reaction core pressure vessel pressure inlet direction in horizontal plane, enter with reactor pressure vessel
Mouth pressure inlet connects.
7. passive PWR nuclear power plant reactor coolant loop as claimed in claim 6 is arranged, it is characterised in that described
Cold section of bend pipe of main pipeline is overall bend pipe.
8. passive PWR nuclear power plant reactor coolant loop as claimed in claim 1 is arranged, it is characterised in that described
Main pipe hot leg, after the outside segment distance in reactor coolant inlet nozzle mouth direction, is 1.5-3 by a bending radius
Times caliber, angle of bend is that the hot segment of bent pipe of main pipeline of 30 °～60 ° turns to steam generator pressure inlet radial direction side in three-dimensional surface
To, it is connected with steam generator entrance sleeve mouth.
9. passive PWR nuclear power plant reactor coolant loop as claimed in claim 8 is arranged, it is characterised in that described
Hot segment of bent pipe of main pipeline is overall bend pipe, and the pressure inlet that only one of which forging integrated therewith connects
Priority Applications (1)
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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 |
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Application publication date: 20161109 |