CN106373620A - Pressurized-water nuclear reactor structure - Google Patents
Pressurized-water nuclear reactor structure Download PDFInfo
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- CN106373620A CN106373620A CN201610875816.8A CN201610875816A CN106373620A CN 106373620 A CN106373620 A CN 106373620A CN 201610875816 A CN201610875816 A CN 201610875816A CN 106373620 A CN106373620 A CN 106373620A
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- Prior art keywords
- assembly
- reactor
- pressure vessel
- heap
- top cover
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
- G21C1/086—Pressurised water reactors
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
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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
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/035—Moderator- or coolant-level detecting devices
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/33—Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
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- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a pressurized-water nuclear reactor structure. The structure comprises a distributed reactor top, a driving mechanism, a pressure container, an in-reactor member and a heat preservation member. The distributed reactor top is connected with a top cover of the pressure container, the heat preservation member is arranged on the outer surface of the pressure container, the in-reactor member is hung on a supporting step of the pressure container, and the driving mechanism is installed on the top cover of the pressure container. It is achieved that a neutron flux measuring detector, a temperature measuring detector and a water-level measuring detector are guided out of a reactor through an in-reactor measuring guiding structure located in an upper end socket of the pressure container and a penetration piece at the top of the pressure container, and it is avoided that the number of in-reactor measuring pipe bases on the top cover is increased; the water level measuring requirements can be met; the quantity of a coolant entering a reactor core is reasonably distributed; due to the heat preservation layer, the advantage that the external of the pressure container of the reactor can be rapidly cooled can also be achieved.
Description
Technical field
The present invention relates to pressurized water nuclear reactor research field, more particularly, to a kind of pressurized water nuclear reactor structure.
Background technology
Acp1000 pressurized water type reactor is three generations's pressurized water type reactor of Chinese autonomy-oriented design, and acp1000 presurized water reactor is adopted
Form reactor core with 177 group fuel assemblies, the seismic acceleration of 0.3g will be born, reactor lifetime extends to 60 years.
With respect to secondary and secondary Fortschrittlicher Druckwasser Reaktor, three generations's pressurized water type reactor eliminates positioned at reactor pressure vessel
The neutron measurement instrument sleeve pipe of bottom (head) and neutron measurement base, by neutron flux measurement detector, temperature measuring probe and
Level measuring detector is by measurement guide frame and pressure vessel top penetration piece in the heap in pressure vessel upper cover
Draw reactor, the quantity thereby resulting in measurement base in heap on top cover greatly increases, the position of heap roof construction equipment,
Structure etc. is required for doing corresponding adjustment, so that whole heap roof construction needs to redesign, brings low head flow simultaneously
The problem of maldistribution, need to design new lower chambers flow distribution structure, additionally, for realizing reactor pressure during major accident
The outside of container quickly cools down, and also needs to design new heat insulation layer structure.
In sum, during present inventor's inventive technique scheme in realizing the embodiment of the present application, in discovery
At least there is following technical problem in technology of stating:
In the prior art, existing pressurized water nuclear reactor structure presence design is unreasonable, and neutron flux measurement is being detected
Device, temperature measuring probe and level measuring detector by the heap in pressure vessel upper cover measurement guide frame and
When pressure vessel top penetration piece draws reactor, the quantity measuring base in heap on top cover is caused to greatly increase, and lower envelope
Head assignment of traffic is unreasonable, the poor technical problem of reactor pressure vessel cooling effect.
Content of the invention
The invention provides a kind of pressurized water nuclear reactor structure, solve existing pressurized water nuclear reactor structure and exist
Design unreasonable, by neutron flux measurement detector, temperature measuring probe and level measuring detector by positioned at pressure
When measurement guide frame and pressure vessel top penetration piece draw reactor in heap in container upper cover, cause heap on top cover
The quantity of interior measurement base greatly increases, and low head assignment of traffic is unreasonable, and reactor pressure vessel cooling effect is poor
Technical problem, it is achieved that accommodating and supporting 177 group fuel assemblies, realizes 60 year life-span of reactor, realizes surveying neutron flux
Amount detector, temperature measuring probe and level measuring detector are by measurement guiding in the heap in pressure vessel upper cover
Structure and pressure vessel top penetration piece draw reactor；Enable level measuring requirement；Realizing in-pile component proper function
Precondition under, reasonable distribution enter reactor core coolant flow；Additionally, heap roof construction not only can meet the functional requirement of heap top but also
Neutron flux measurement detector, temperature measuring probe and level measuring detector can be met after Base top contact to working place
Requirement；Heat-insulation layer also can achieve the technique effect of the outside quick cooling of reactor pressure vessel.
For solving above-mentioned technical problem, the embodiment of the present application provides a kind of pressurized water nuclear reactor structure, described structure
Including:
Distributing heap top, drive mechanism, pressure vessel, in-pile component, heat preservation structural component, described distributing heap top top and described pressure
The top cover of container connects, and described heat preservation structural component is arranged on described pressure vessel outer surface, and described in-pile component is hung in described pressure
On the support level of force container, described drive mechanism is arranged on pressure vessels top cover, and wherein, described distributing heap top is specifically wrapped
Include: ventilator cowling supporting, leeward shade assembly, cooling coaming plate, guided way, wind pipe component, antidetonation supporting arrangement, cable tray, cable
Axle assemble, top cover suspender superstructure, lower suspension rod, wherein, ventilator cowling supporting is fixed together with pressure vessels top cover, lower fan housing
Assembly is fixed in ventilator cowling supporting, and cooling coaming plate and wind pipe component are fixed on leeward shade assembly；Lower downrod lower end and pressure
Container hanger connects, and lower end is connected with top cover suspender superstructure, and antidetonation supporting arrangement is fixed on lower suspension rod, cable tray with
Cable axle assemble is fixed on above antidetonation supporting arrangement.
Wherein, described pressure vessel includes: cap assembly, container assemblies, fit sealing part, wherein, described cap assembly
Connect with described container assemblies, and fit sealing is carried out by described fit sealing part.
Wherein, described in-pile component includes: holddown spring, upper-part in-reactor component, bottom in-pile component, u shape insert, its
In, in-pile component is structure of the prior art, and its structure annexation refers to patent 201210574578.9.
Wherein, described upper-part in-reactor component includes: upper bearing assembly, control rod guide tubes and bundles assembly, upper core plate assembly, heap
Interior measurement guide frame, upper supporting column assembly, level measuring supporting column assembly；Described bottom in-pile component includes: hanging basket assembly,
Secondary supporting and assignment of traffic assembly.
Wherein, described heat preservation structural component includes: metallic insulation, metallic insulation supporting, water injection pipe, liner plate, reactor pit, water inlet
Mouth assembly, soda pop Exhaust assembly.
The one or more technical schemes providing in the embodiment of the present application, at least have the following technical effect that or advantage:
It is including distributing heap top, drive mechanism, pressure vessel, heap due to employing pressurized water nuclear reactor structure design
Inner member, heat preservation structural component, described distributing heap top top is connected with the top cover of described pressure vessel, and described heat preservation structural component is arranged on institute
State pressure vessel outer surface, described in-pile component is hung on the support level of described pressure vessel, and described drive mechanism is installed
On pressure vessels top cover, wherein, described distributing heap top specifically includes: ventilator cowling supporting, leeward shade assembly, cooling coaming plate,
Guided way, wind pipe component, antidetonation supporting arrangement, cable tray, cable axle assemble, top cover suspender superstructure, lower suspension rod, its
In, ventilator cowling supporting be fixed together with pressure vessels top cover, leeward shade assembly be fixed on ventilator cowling supporting on, cooling coaming plate with
Wind pipe component is fixed on leeward shade assembly；Lower downrod lower end is connected with pressure vessel hanger, and lower end is tied with top cover suspender top
Structure connects, and antidetonation supporting arrangement is fixed on lower suspension rod, and cable tray and cable axle assemble are fixed on above antidetonation supporting arrangement,
So, efficiently solving existing pressurized water nuclear reactor structure, to there is design unreasonable, by neutron flux measurement detector,
Temperature measuring probe and level measuring detector are by measurement guide frame and pressure in the heap in pressure vessel upper cover
When force container top penetration piece draws reactor, the quantity measuring base in heap on top cover is caused to greatly increase, and low head
Assignment of traffic is unreasonable, the poor technical problem of reactor pressure vessel cooling effect, and then achieves and can accommodate and support 177
Group fuel assembly, realizes 60 year life-span of reactor, realizes surveying neutron flux measurement detector, temperature measuring probe and water level
Amount detector is drawn anti-by measurement guide frame in the heap in pressure vessel upper cover and pressure vessel top penetration piece
Answer heap, it is to avoid in heap on top cover, the quantity of measurement base increases；Enable level measuring requirement；Should be active realizing in-pile component
Under the precondition of energy, reasonable distribution enters the coolant flow of reactor core；Additionally, heap roof construction both can meet the functional requirement of heap top
Neutron flux measurement detector, temperature measuring probe and level measuring detector can be met empty to operation after Base top contact again
Between requirement；Heat-insulation layer also can achieve the technique effect of the outside quick cooling of reactor pressure vessel.
Brief description
Fig. 1 is the structural representation of pressurized water nuclear reactor structure in the embodiment of the present application one；
Fig. 2 is the structural representation on distributing heap top in the embodiment of the present application one；
Fig. 3 is the structural representation of pressure vessel in the embodiment of the present application one；
Fig. 4 be in the embodiment of the present application one in-pile component structural representation；
Fig. 5 is the structural representation of the embodiment of the present application one middle and upper part in-pile component；
Fig. 6 is the structural representation of the embodiment of the present application one middle and lower part in-pile component；
Fig. 7 is the structural representation of heat preservation structural component in the embodiment of the present application one；
Wherein, 1- distributing heap top；2- drive mechanism；3- pressure vessel；4- in-pile component；5- heat preservation structural component；6- pressure vessel
Top cover；7- ventilator cowling supports；8- leeward shade assembly；9- cools down coaming plate；10- guided way；11- wind pipe component；12- antidetonation is propped up and is taken up
Put；13a- cable tray；13b- cable axle assemble；14- top cover suspender superstructure；Suspension rod under 15-；16- kingbolt；17- holds
Device assembly；18- holddown spring；19- upper-part in-reactor component；20- bottom in-pile component；21-u shape insert；Supporting group on 22-
Part；23- control rod guide tubes and bundles assembly；24- upper core plate assembly；Measurement guide frame in 25- heap；Column assembly is supported on 26-；
27- level measuring supports column assembly；28- hanging basket assembly；Bis- supportings of 29a-；29b- assignment of traffic assembly；30- water injection pipe；31-
Water inlet assembly；32- metallic insulation supports；33- liner plate；34- reactor pit；35- soda pop Exhaust assembly, 36- metallic insulation.
Specific embodiment
The invention provides a kind of pressurized water nuclear reactor structure, solve existing pressurized water nuclear reactor structure and exist
Design unreasonable, by neutron flux measurement detector, temperature measuring probe and level measuring detector by positioned at pressure
When measurement guide frame and pressure vessel top penetration piece draw reactor in heap in container upper cover, cause heap on top cover
The quantity of interior measurement base greatly increases, and low head assignment of traffic is unreasonable, and reactor pressure vessel cooling effect is poor
Technical problem, it is achieved that accommodating and supporting 177 group fuel assemblies, realizes 60 year life-span of reactor, realizes surveying neutron flux
Amount detector, temperature measuring probe and level measuring detector are by measurement guiding in the heap in pressure vessel upper cover
Structure and pressure vessel top penetration piece draw reactor；Enable level measuring requirement；Realizing in-pile component proper function
Precondition under, reasonable distribution enter reactor core coolant flow；Additionally, heap roof construction not only can meet the functional requirement of heap top but also
Neutron flux measurement detector, temperature measuring probe and level measuring detector can be met after Base top contact to working place
Requirement；Heat-insulation layer also can achieve the technique effect of the outside quick cooling of reactor pressure vessel.
Technical scheme during the application is implemented is to solve above-mentioned technical problem.General thought is as follows:
Employing pressurized water nuclear reactor structure design is including structure in: distributing heap top, drive mechanism, pressure vessel, heap
Part, heat preservation structural component, described distributing heap top top is connected with the top cover of described pressure vessel, and described heat preservation structural component is arranged on described pressure
Force container outer surface, described in-pile component is hung on the support level of described pressure vessel, and described drive mechanism is arranged on pressure
On force container top cover, wherein, described distributing heap top specifically includes: ventilator cowling supporting, leeward shade assembly, cooling coaming plate, guiding
Rail, wind pipe component, antidetonation supporting arrangement, cable tray, cable axle assemble, top cover suspender superstructure, lower suspension rod, wherein, lead to
Fan housing supporting is fixed together with pressure vessels top cover, and leeward shade assembly is fixed in ventilator cowling supporting, cools down coaming plate and airduct
Assembly is fixed on leeward shade assembly；Lower downrod lower end is connected with pressure vessel hanger, and lower end is with top cover suspender superstructure even
Connect, antidetonation supporting arrangement is fixed on lower suspension rod, cable tray and cable axle assemble are fixed on above antidetonation supporting arrangement, institute
So that efficiently solving existing pressurized water nuclear reactor structure, to there is design unreasonable, by neutron flux measurement detector, temperature
Degree measurement detector and level measuring detector are by measurement guide frame and pressure in the heap in pressure vessel upper cover
When container top penetration piece draws reactor, the quantity measuring base in heap on top cover is caused to greatly increase, and low head stream
Amount unreasonable distribution, the poor technical problem of reactor pressure vessel cooling effect, and then achieve and can accommodate and support 177 groups
Fuel assembly, realizes 60 year life-span of reactor, realizes neutron flux measurement detector, temperature measuring probe and level measuring
Detector draws reaction by measurement guide frame in the heap in pressure vessel upper cover and pressure vessel top penetration piece
Heap, it is to avoid in heap on top cover, the quantity of measurement base increases；Enable level measuring requirement；Realizing in-pile component proper function
Precondition under, reasonable distribution enter reactor core coolant flow；Additionally, heap roof construction not only can meet the functional requirement of heap top but also
Neutron flux measurement detector, temperature measuring probe and level measuring detector can be met after Base top contact to working place
Requirement；Heat-insulation layer also can achieve the technique effect of the outside quick cooling of reactor pressure vessel.
In order to be better understood from technique scheme, below in conjunction with Figure of description and specific embodiment to upper
State technical scheme to be described in detail.
Embodiment one:
In embodiment one, there is provided a kind of pressurized water nuclear reactor structure, refer to Fig. 1-Fig. 7, described structure includes:
Distributing heap top 1, drive mechanism 2, pressure vessel 3, in-pile component 4, heat preservation structural component 5, described distributing heap top with described
Pressure vessels top cover 6 connects, and described heat preservation structural component is arranged on described pressure vessel outer surface, and described in-pile component is hung described
On the support level of pressure vessel, described drive mechanism is arranged on pressure vessels top cover, and wherein, described distributing heap top is concrete
Including: ventilator cowling supporting 7, leeward shade assembly 8, cooling coaming plate 9, guided way 10, wind pipe component 11, antidetonation supporting arrangement 12, electricity
Cable bracket 13a, cable axle assemble 13b, top cover suspender superstructure 14, lower suspension rod 15, wherein, ventilator cowling supports and pressure vessel
Top cover is fixed together, and leeward shade assembly is fixed in ventilator cowling supporting, and cooling coaming plate and wind pipe component are fixed on lower fan housing group
On part；Lower downrod lower end is connected with pressure vessel hanger, and lower end is connected with top cover suspender superstructure, and antidetonation supporting arrangement is fixed
On lower suspension rod, cable tray and cable axle assemble are fixed on above antidetonation supporting arrangement.
Wherein, in the embodiment of the present application, distributing heap top is connected to the container assemblies of pressure vessel by kingbolt 16
On 17, drive mechanism is by actuated lever assemblies, hook assembly, pneumatic shell, coil block, stick location probe assembly and collet assembly
Composition；Actuated lever assemblies pass through from the quill endoporus of hook assembly, move up and down in pneumatic shell；Hook assembly is arranged on
In capsul, upper end is fixed, lower end radial positioning；Pneumatic shell is the pressure-containing member of drive mechanism, by driving throw of lever sleeve pipe group
Part and sealing shell component composition, are driven throw of lever thimble assembly to be connected by trapezoidal thread and install with little ω sealing ring welded seal
In sealing shell component upper end, sealing shell component is welded together with pressure vessels top cover by penetration piece；Coil block is enclosed within close
The outside of capsule assembly.Stick location probe assembly is arranged on outside driving throw of lever thimble assembly；Collet assembly is arranged on close
Capsule component bottom.
In-pile component is hung on the support level of pressure vessel, neutron flux measurement detector, temperature measuring probe
With level measuring detector by " upper-part in-reactor component for pressurized water reactor is arranged " in pressure vessel upper cover
(cn200980150445.5) the In-core Instrumentation base of structure and pressure vessels top cover and level measuring base draw reactor,
Outside reactor pressure vessel, heat preservation structural component is set, covers whole pressure vessel outer surface, pressure vessel import and export adapter with
On heat preservation structural component be seated in pressure vessel outer surface, import and export the following heat preservation structural component of adapter and be suspended in heap crater wall.
Wherein, in the embodiment of the present application, the distributing heap in the application withstands on and meets PRV head package structure function
Meanwhile, also have the following characteristics that the fan housing coaming plate height in leeward shade assembly is less and outward-dipping, thus increased heap
The working place of interior measurement sealing structure；Pressure vessels top cover arranges four hangers, hangs under setting four in top cover suspender
Bar is thus avoid lower suspension rod interfering with vertical airduct, so that cowl structure is more regular, runner problem evenly, full
The limit value of foot drive mechanism inhomogeneous cooling even coefficient requires, thus reaching the uniform purpose cooling down drive mechanism；Divulge information simultaneously
The radial dimension of shade assembly disclosure satisfy that the use requirement of bolt stretching machine.
Wherein, in the embodiment of the present application, described pressure vessel (cn 203325479 u) includes: cap assembly, container
Assembly, fit sealing part, wherein, described cap assembly and described container assemblies connect, and are carried out by described fit sealing part
Fit sealing.
Wherein, in actual applications, the Nomenclature Composition and Structure of Complexes of pressure vessel refer in patent documentation cn 203325479 u
Corresponding description, here is omitted.
Wherein, in the embodiment of the present application, 60 can be met by what cap assembly, container assemblies, fit sealing part etc. formed
The pressure vessel of year reliability.
Structural feature is particularly as follows: 1) increase the internal diameter of reactor core cylinder, make cylinder metal farthest leave reactor core, decline
Chamber water gap increases, and reactor core section cylinder material is reduced by fast neutron fluence, thus reducing the possibility of pressure vessel brittle break
Property.
2) lengthen the length of reactor core section cylinder, make the girth joint at cylinder two ends leave active region, that is, in the range of active region no
Radiation sensitivity is higher than the weld metal of base metals.
3) cancel reactor pressure vessel bottom penetration piece, eliminate and occur leakage to lead because of reactor pressure vessel low head
Cause the accident of coolant loss, increase the drag of core meltdown simultaneously, reduce inservice inspection and potentially repair.
Material main points: 1) reduce reactor pressure vessel material of main part 16mnd5(sa508-3) irradiation is quick in low-alloy steel
Sense constituent content, p≤0.008% in reactor core cylinder forgings, changeover portion and nozzle belt, s≤0.005%, cu≤0.05%；Other forgings
P≤0.008% in part, s≤0.005%, cu≤0.08%.In addition, controlling the cobalt content of stainless steel material it is desirable to as little as 0.06%.
2) reactor pressure vessel material of main part rtndt temperature, reactor core cylinder forgings rtndt≤- 23.3 DEG C, other forging are reduced
Rtndt≤- 20 DEG C, reactor core cylinder two ends Low Alloy Steel Welds deposited metal rtndt≤- 28.9 DEG C.
Wherein, in the embodiment of the present application, described in-pile component includes: holddown spring 18, upper-part in-reactor component 19, bottom
In-pile component 20, u shape insert 21.
Wherein, in the embodiment of the present application, in-pile component (201210574578.9) its structure can accommodate and support 177 groups
Fuel assembly；Enable level measuring requirement；Enable to survey neutron flux measurement detector, temperature measuring probe and water level
Amount detector is drawn anti-by measurement guide frame in the heap in pressure vessel upper cover and pressure vessel top penetration piece
Answer the requirement of heap；Meanwhile, under the precondition realizing in-pile component proper function, reasonable distribution enters the coolant flow of reactor core
Amount.
Wherein, in the embodiment of the present application, described upper-part in-reactor component includes: upper bearing assembly 22, control rod guide tubes and bundles
Measurement guide frame 25, upper supporting column assembly 26, level measuring supporting column assembly 27 in assembly 23, upper core plate assembly 24, heap；
Described bottom in-pile component includes: hanging basket assembly 28, secondary supporting 29a and assignment of traffic assembly 29b.
Wherein, in actual applications, the structure and composition of in-pile component refer to patent documentation cn201210574578.9
In describe accordingly, here is omitted.
Wherein, in the embodiment of the present application, its structure of upper-part in-reactor component enables level measuring requirement；In enabling to incite somebody to action
Sub- flux measurement detector, temperature measuring probe and level measuring detector are by the heap in pressure vessel upper cover
Measurement guide frame and the requirement of pressure vessel top penetration piece extraction reactor.
Wherein, in the embodiment of the present application, its structure can accommodate and support 177 group fuel assemblies；Meanwhile, realizing in heap
Under the precondition of component proper function, reasonable distribution enters the coolant flow of reactor core.
Wherein, in the embodiment of the present application, described heat preservation structural component (cn202650559u) includes: metallic insulation 36, gold
Belong to heat-insulation layer supporting 32, water injection pipe 30, liner plate 33, reactor pit 34, water inlet assembly 31, soda pop Exhaust assembly 35.
Wherein, in actual applications, the structure and composition of heat preservation structural component refer in patent documentation cn202650559u
Description, here is omitted.
Wherein, in the embodiment of the present application, cooling water is directly entered reactor pressure vessel and insulation by filling pipe
In the ring cavity of layer；Water inlet assembly is not provided with cover plate.
Technical scheme in above-mentioned the embodiment of the present application, at least has the following technical effect that or advantage:
It is including integrated heap top, drive mechanism, pressure vessel, heap due to employing pressurized water nuclear reactor structure design
Inner member, heat preservation structural component, described integration heap top is connected with the top cover of described pressure vessel, and described heat preservation structural component is arranged on described
Pressure vessel outer surface, described in-pile component is hung on the support level of described pressure vessel, and described drive mechanism is arranged on
On pressure vessels top cover, wherein, described integration heap top specifically includes: lower suspension rod, cooling coaming plate, shroud, antidetonation assembly, top cover
Suspender, Electric cable tray assembly, cooling duct, wherein, described lower suspension rod and described cooling duct are installed in described
In shroud, described lower suspension rod is connected with the hanger on the top cover of described pressure vessel, and described cooling coaming plate is arranged on described shroud
Inwall on, described antidetonation assembly, described top cover suspender, described cable tray, described cable axle assemble be installed in described in enclose
The technical scheme at cylinder top, so, efficiently solve existing pressurized water nuclear reactor structure presence design unreasonable, in inciting somebody to action
Sub- flux measurement detector, temperature measuring probe and level measuring detector are by the heap in pressure vessel upper cover
When measurement guide frame and pressure vessel top penetration piece draw reactor, cause the quantity measuring base in heap on top cover big
Big increase, and low head assignment of traffic is unreasonable, the poor technical problem of reactor pressure vessel cooling effect, and then achieve
Can accommodate and supporting 177 group fuel assemblies, realize 60 year life-span of reactor, realize surveying neutron flux measurement detector, temperature
Amount detector and level measuring detector are by measurement guide frame and pressure vessel in the heap in pressure vessel upper cover
Top penetration piece draws reactor, it is to avoid in heap on top cover, the quantity of measurement base increases；Enable level measuring requirement；In reality
Under the precondition of existing in-pile component proper function, reasonable distribution enters the coolant flow of reactor core；Additionally, heap roof construction both may be used
Meet the functional requirement of heap top and can meet neutron flux measurement detector, temperature measuring probe and level measuring detector from top again
Requirement to working place after portion's extraction；Heat-insulation layer also can achieve the technique effect of the outside quick cooling of reactor pressure vessel.
Although preferred embodiments of the present invention have been described, but those skilled in the art once know basic creation
Property concept, then can make other change and modification to these embodiments.So, claims are intended to be construed to including excellent
Select embodiment and fall into being had altered and changing of the scope of the invention.
Obviously, those skilled in the art can carry out the various changes and modification essence without deviating from the present invention to the present invention
God and scope.So, if these modifications of the present invention and modification belong to the scope of the claims in the present invention and its equivalent technologies
Within, then the present invention is also intended to comprise these changes and modification.
Claims (5)
1. a kind of pressurized water nuclear reactor structure is it is characterised in that described structure includes:
Distributing heap top, drive mechanism, pressure vessel, in-pile component, heat preservation structural component, described distributing heap top top and described pressure
The top cover of container connects, and described heat preservation structural component is arranged on described pressure vessel outer surface, and described in-pile component is hung in described pressure
On the support level of force container, described drive mechanism is arranged on pressure vessels top cover, and wherein, described distributing heap top is specifically wrapped
Include: ventilator cowling supporting, leeward shade assembly, cooling coaming plate, guided way, wind pipe component, antidetonation supporting arrangement, cable tray, cable
Axle assemble, top cover suspender superstructure, lower suspension rod, wherein, ventilator cowling supporting is fixed with pressure vessels top cover, and leeward shade assembly is solid
It is scheduled in ventilator cowling supporting, cooling coaming plate and wind pipe component are fixed on leeward shade assembly；Lower downrod lower end is hung with pressure vessel
Ear connects, and lower end is connected with top cover suspender superstructure, and antidetonation supporting arrangement is fixed on lower suspension rod, cable tray and cable bridge
Assembly is fixed on above antidetonation supporting arrangement.
2. structure according to claim 1 is it is characterised in that described pressure vessel includes: cap assembly, container assemblies,
Fit sealing part, wherein, described cap assembly and described container assemblies connect, and carry out fastening close by described fit sealing part
Envelope.
3. structure according to claim 1 is it is characterised in that described in-pile component includes: structure in holddown spring, top heap
Part, bottom in-pile component, u shape insert.
4. structure according to claim 3 is it is characterised in that described upper-part in-reactor component includes: upper bearing assembly, control
Measurement guide frame, upper supporting column assembly, level measuring supporting column assembly in excellent guide assembly, upper core plate assembly, heap；Institute
State bottom in-pile component to include: hanging basket assembly, secondary supporting and assignment of traffic assembly.
5. structure according to claim 1 is it is characterised in that described heat preservation structural component includes: metallic insulation, metal heat preservation
Layer supporting, water injection pipe, liner plate, reactor pit, water inlet assembly, soda pop Exhaust assembly.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610875816.8A CN106373620A (en) | 2016-10-08 | 2016-10-08 | Pressurized-water nuclear reactor structure |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610875816.8A CN106373620A (en) | 2016-10-08 | 2016-10-08 | Pressurized-water nuclear reactor structure |
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| CN106373620A true CN106373620A (en) | 2017-02-01 |
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| CN201610875816.8A Pending CN106373620A (en) | 2016-10-08 | 2016-10-08 | Pressurized-water nuclear reactor structure |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108039211A (en) * | 2017-12-08 | 2018-05-15 | 中国核动力研究设计院 | Barricade in presurized water reactor integration heap top and the heap top |
| CN108206061A (en) * | 2017-12-01 | 2018-06-26 | 肇庆鼎湖檀树电子科技有限公司 | Nuclear power power generator |
| CN110706831A (en) * | 2019-11-14 | 2020-01-17 | 中核核电运行管理有限公司 | Bottom heat preservation and insulation device and method for primary circuit voltage stabilizer of nuclear power plant |
| CN111667934A (en) * | 2020-06-19 | 2020-09-15 | 中国核动力研究设计院 | Loading and unloading method for layered arrangement driving mechanism of nuclear reactor test reactor |
| CN112037941A (en) * | 2020-07-28 | 2020-12-04 | 中广核核电运营有限公司 | Pressure vessel top cover supporting device and supporting method |
| CN112782212A (en) * | 2020-12-29 | 2021-05-11 | 安徽应流集团霍山铸造有限公司 | Nuclear power metal heat preservation heat transfer performance test device |
| CN114373560A (en) * | 2021-12-16 | 2022-04-19 | 华能核能技术研究院有限公司 | Modular high-temperature gas cooled reactor internal power detection model |
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108206061A (en) * | 2017-12-01 | 2018-06-26 | 肇庆鼎湖檀树电子科技有限公司 | Nuclear power power generator |
| CN108039211A (en) * | 2017-12-08 | 2018-05-15 | 中国核动力研究设计院 | Barricade in presurized water reactor integration heap top and the heap top |
| CN110706831A (en) * | 2019-11-14 | 2020-01-17 | 中核核电运行管理有限公司 | Bottom heat preservation and insulation device and method for primary circuit voltage stabilizer of nuclear power plant |
| CN111667934A (en) * | 2020-06-19 | 2020-09-15 | 中国核动力研究设计院 | Loading and unloading method for layered arrangement driving mechanism of nuclear reactor test reactor |
| CN111667934B (en) * | 2020-06-19 | 2022-04-15 | 中国核动力研究设计院 | Loading and unloading method for layered arrangement driving mechanism of nuclear reactor test reactor |
| CN112037941A (en) * | 2020-07-28 | 2020-12-04 | 中广核核电运营有限公司 | Pressure vessel top cover supporting device and supporting method |
| CN112782212A (en) * | 2020-12-29 | 2021-05-11 | 安徽应流集团霍山铸造有限公司 | Nuclear power metal heat preservation heat transfer performance test device |
| CN114373560A (en) * | 2021-12-16 | 2022-04-19 | 华能核能技术研究院有限公司 | Modular high-temperature gas cooled reactor internal power detection model |
| CN114373560B (en) * | 2021-12-16 | 2023-05-16 | 华能核能技术研究院有限公司 | Modular high-temperature gas cooled reactor internal power detection model |
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