CN207337936U - Core-container joint device - Google Patents
Core-container joint device Download PDFInfo
- Publication number
- CN207337936U CN207337936U CN201720778972.2U CN201720778972U CN207337936U CN 207337936 U CN207337936 U CN 207337936U CN 201720778972 U CN201720778972 U CN 201720778972U CN 207337936 U CN207337936 U CN 207337936U
- Authority
- CN
- China
- Prior art keywords
- core
- pump
- container joint
- joint device
- guide assembly
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Fee Related
Links
- 239000012530 fluid Substances 0.000 claims abstract description 29
- 238000005086 pumping Methods 0.000 claims abstract description 9
- 238000004891 communication Methods 0.000 claims abstract description 5
- 239000008358 core component Substances 0.000 claims description 15
- 238000007789 sealing Methods 0.000 claims description 2
- 239000002826 coolant Substances 0.000 description 35
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 26
- 229910052708 sodium Inorganic materials 0.000 description 26
- 239000011734 sodium Substances 0.000 description 26
- 239000000446 fuel Substances 0.000 description 16
- 239000000306 component Substances 0.000 description 14
- 238000006243 chemical reaction Methods 0.000 description 11
- 238000002485 combustion reaction Methods 0.000 description 5
- 239000007789 gas Substances 0.000 description 4
- 239000007788 liquid Substances 0.000 description 4
- 238000001816 cooling Methods 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 239000003758 nuclear fuel Substances 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 230000001681 protective effect Effects 0.000 description 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 2
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 description 1
- 102000005393 Sodium-Potassium-Exchanging ATPase Human genes 0.000 description 1
- 108010006431 Sodium-Potassium-Exchanging ATPase Proteins 0.000 description 1
- 229910052776 Thorium Inorganic materials 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 230000001195 anabolic effect Effects 0.000 description 1
- 229910052786 argon Inorganic materials 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 230000012447 hatching Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 230000002209 hydrophobic effect Effects 0.000 description 1
- 238000011065 in-situ storage Methods 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000003032 molecular docking Methods 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 238000002139 neutron reflectometry Methods 0.000 description 1
- BITYAPCSNKJESK-UHFFFAOYSA-N potassiosodium Chemical compound [Na].[K] BITYAPCSNKJESK-UHFFFAOYSA-N 0.000 description 1
- 239000003507 refrigerant Substances 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 230000003068 static effect Effects 0.000 description 1
- 230000008646 thermal stress Effects 0.000 description 1
- 230000001052 transient effect Effects 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
A kind of core container joint device is the utility model is related to, which has base portion, which includes being configured to the container joint portion contacted with reactor vessel.The pump guide assembly being connected with base portion, which limits, to be configured to pumping the pump guiding piece docked.Core supporting part is limited by base portion and is configured to receive a part for reactor core.Fluid passage will pump guiding piece and be in fluid communication with core supporting part.
Description
Technical field
It the utility model is related to nuclear reaction field, more particularly to a kind of core-container joint device.
Background technology
Fission-type reactor includes propagation-burning fast reaction heap (also referred to as traveling wave reactor, or TWR).TWR refer to by
It is designed to use natural uranium, depleted uranium, weary light-water reactor fuel or thorium indefinitely to transport as heavily loaded fuel after starting
Turn and wherein propagation and with the reactor that will advance relative to fuel of ripple of after-combustion.Therefore, in some respects, TWR be according to
Lai Yu breeds the through type fast reaction heap of the subcritical heavily loaded operating fuel to upstate and combustion in situ.In TWR, increase
Grow and central core of the ripple of fissioning (" propagation-combustion wave ") originating from reactor in and move relative to fuel.It is quiet in fuel
In the case of only, propagation and combustion wave are from burning point to external expansion.In some cases, fuel is moveable so as to breed and burns
Ripple is moved relative to core static (for example, standing wave) but relative to fuel；Standing wave should be considered as a kind of TWR.The shifting of fuel assembly
It is dynamic be known as " fuel exchange (fuel shuffling) and standing wave can be completed, this be to reactor characteristic (heat, flux, power,
Fuel combustion etc.) adjusting." central core that wherein fuel assembly is switched configured in reactor vessel.Fuel assembly bag
Include fission nuclear fuel component and the nuclear fuel assembly of fissile material can be produced.It can also configure in central core and be useful for adjusting instead
Answer the reaction controlling component of heap characteristic.
The fission energy limited by standing wave forms thermal energy, and the thermal energy is through one or more Main Coolant loops and centre
Coolant loop is continuously delivered to steam generator to generate electricity, and Low Temperature Thermal is arranged by one group of water-cooled vacuum condenser
Remove.Coolant system is separated into Main Coolant loop and intercoolant loop helps to maintain core and Main Coolant loop
Integrality.In TWR, Main Coolant loop and intercoolant loop are both using Liquid Sodium as cooling agent.
Utility model content
On the one hand, a kind of core-container joint device is the utility model is related to, it has：Base portion, the base portion include structure
Cause the container joint portion contacted with reactor vessel；The first pump guide assembly being connected with base portion, the first pump guide assembly
Limit the first pump guiding piece for being configured to dock with the first pump；Core supporting part, which is limited by base portion and structure
Cause a part for receiving reactor core；And fluid passage, the fluid passage pump guiding piece and core supporting part stream by first
Body connects.In one example, container joint portion includes basic ring.In another example, the first pump guiding piece includes seal, institute
State seal and be configured to accommodate axial movement of the first pump guiding piece relative to the first pump.In another example, seal is located at
Above core supporting part.In yet another example, core-container joint further includes the second pump guide assembly being connected with base portion,
The second pump guide assembly limits the second pump guiding piece for being configured to dock with the second pump；With second fluid passage, the second
Second pump guiding piece is in fluid communication body passage with core supporting part.
In another example of above-mentioned aspect, the first pump guide assembly and the second pump guide assembly are located at opposite the two of base portion
Side.In one example, core supporting part provides both lateral support and vertical support to reactor core.In another example
In, base portion limits the inner space for including multiple fluid passages.In another example, base portion has circular cone shape.Another again
In one example, the first pump guide assembly extending sideways from base portion.
In another example of above-mentioned aspect, the first pump guide assembly includes pump guide assembly passage, the pump guide assembly
Passage has spherical portion and connects the outlet fluid in the pumping chamber below the first pump discharge and reactor core component
It is logical.In one example, pumping guide assembly passage includes two outlets and an entrance.
Brief description of the drawings
The attached drawing for forming the part of the utility model below is illustrative for described technology and not anticipates
The scope of the technology of patent right is required in limitation in any way, which should be based on claim appended herein.
Fig. 1 is shown in block diagram form some basic building blocks of traveling wave reactor.
Fig. 2 is the perspective view of other components of core-container joint device and traveling wave reactor.
Fig. 3 is the perspective section view of core-container joint device shown in the Fig. 2 for the various components for including traveling wave reactor
Figure.
Fig. 4 is the sectional view of the core-container joint device and reaction pile element shown in Fig. 3.
Fig. 5 is the birds-eye perspective of core-container joint device in Fig. 2-4.
Fig. 6 is the face upwarding view of core-container joint device in Fig. 2-4.
Fig. 7 is the side plan view of core-container joint device in Fig. 2-4.
Fig. 8 is the front plan view of core-container joint device in Fig. 2-4.
Fig. 9 is the plan view from above of core-container joint device in Fig. 2-4.
Figure 10 is the sectional view along core-container joint device in Fig. 2-4 of the hatching A-A shown in Fig. 9.
Figure 11 is the face upwarding view of core-container joint device in Fig. 2-4.
Embodiment
Fig. 1 is shown in block diagram form some basic building blocks of traveling wave reactor (TWR) 100.In general, TRW100 includes
Accommodate the reactor core 102 of multiple fuel assembly (not shown).Core 102, which configures, is keeping the liquid sodium cooling of certain volume
In the pond 104 of agent 106.Pond 104 is referred to as hot pond and with higher than also accommodating surrounding's cold drop 108 of Liquid Sodium cooling agent 106
Sodium temperature (being attributed to the energy produced by fuel assembly in reactor core 102).Hot pond 104 passes through elbows
(redan) 110 and cold drop 108 separate.The headroom 112 of the ullage of sodium cooling agent 106 is filled with the lazy of such as argon gas
Property protective gas.Reactor vessel 114 surrounds reactor core 102, hot pond 104 and cold drop 108, and utilizes reactor lid
116 sealings.Reactor lid 116 provides the various maintenance points led in the inside of reactor vessel 114.
The size of reactor core 102 is selected based on Multiple factors, including the characteristic of fuel, desired generated energy, can
100 space of reactor of acquisition etc..The various examples of TWR can as needed or it is expected be used for low-power (about 300MWe- about
500MWe), middle power (about 500MWe- about 1000MWe) and high power (about 1000MWeMore than) application in.Can be by core
102 surroundings set unshowned one or more reflectors to improve reactor 100 so that neutron reflection is returned in core 102
Performance.In addition, can produce fissile material and fissible nuclear component moves (or " switching ") to control in core 102 and around it
Make the nuclear reaction wherein occurred.
The circulation in container 114 via main sodium cooling agent pump 118 of sodium cooling agent 106.Main coolant pump 118 is from cold drop 108
Aspirate sodium cooling agent 106 and it is ejected into pumping chamber (plenum) below reactor core 102.106 quilt of cooling agent
Drive upwardly through core and be heated due to the reaction occurred in reactor core 102.Heated cooling agent 106 from
Hot pond 104 enters (multiple) intermediate heat exchanger 120, and leaves intermediate heat exchanger 120 and reenter cold drop 108.This
Kind of Main Coolant loop 122 thus make the circulation completely in reactor vessel 114 of sodium cooling agent 106.
Intermediate heat exchanger 120 combines and is physically separate from all the time with main sodium pond 104 and 108 that (that is, intermediate sodium and main sodium be forever
Far from mixing) one section of Liquid Sodium closed loop.Heat (is fully accommodated in by intermediate heat exchanger 120 from Main Coolant loop 122
In container 114) it is delivered to intercoolant loop 124 (being positioned only part in container 114).Intermediate heat exchanger 120 passes through
Elbows 110, so as to bridge hot pond 104 and cold drop 108 (to allow the sodium 106 in Main Coolant loop 122 to flow therebetween
It is dynamic).In one example, four intermediate heat exchangers 120 are distributed in container 114.Alternatively, heat exchange among two or six
Device 120 is distributed in container 114.
Intercoolant loop 124 makes the sodium cooling agent 126 through pipeline disengaging container 114 be followed via reactor lid 116
Ring.Middle sodium pump 128 positioned at the outside of reactor vessel 114 circulates sodium cooling agent 126.Heat is from Main Coolant loop 122
Sodium cooling agent 106 be delivered to the sodium cooling agent 126 of the intercoolant loop 124 in intermediate heat exchanger 120.Cooling during rolling
The sodium cooling agent 126 of agent loop 124 passes through multiple pipes 130 in intermediate heat exchanger 120.These pipes 130 keep Main Coolant
The sodium cooling agent 106 of loop 122 is separated with the sodium cooling agent 126 of intercoolant loop 124, while transmits heat therebetween
Energy.
Direct heat exchanger 132 extends into hot pond 104 and usually in case of emergency into Main Coolant loop 122
Sodium cooling agent 106 provide cooling.Direct heat exchanger 132 is configured to allow for sodium cooling agent 106 to be entered and left from hot pond 104
Heat exchanger 132.Direct heat exchanger 132 has the structure similar to intermediate heat exchanger 120, wherein the pipe 134 is kept
The NaK (sodium-potassium) of Main Coolant loop 122 and the direct heat exchanger cooling agent (NaK) of direct reactor coolant loop 138
136 separate, while transferring heat energy therebetween.
Other assisted reaction pile elements (in reactor vessel 114 and outside reactor vessel 114) include
But it is not limited to be not shown but will become apparent to pump to those skilled in the art, is check-valves, shut-off valve, flange, hydrophobic
Groove etc..Through reactor lid 116 other through hole (for example, port, inertia protection gas for main refrigerant pump 118
Body and inspection port, sodium processing and protective gas port etc.) it is not shown.Control system 140 is used to controlling and monitoring anabolic reaction
The various components and system of heap 100.
Broadly, the utility model describes the configuration for the performance for improving the reactor 100 described in Fig. 1.Specifically, use
It is illustrated in example, configuration and the arrangement of supporting and/or core-container joint device of the various components of coupled reaction heap 100
And it is more fully described below with reference to figure below.
Fig. 2-11 shows the various views of exemplary core-container joint device 204 and is described in the lump.Be not with
Each component of lower description is shown in the various figures.In figure, various reaction pile elements have been omitted for clarity.In general, core
Body-container joint device 204 provides the radial direction and vertical non-alignment of pump 206.In some cases, core-container joint device 204
Supporting is provided for reactor core component 208.Core-container joint device 204 is contacted with reactor vessel 202 and in salient angle
The lower section of portion 110 is located in cold drop 108.
It is expected that the temperature rise produced during General reactions stack operation will cause reactor vessel 202 to expand.Since heat increases
It is long, reactor vessel 202 vertically axis, be downwardly and away from reactor roof expansion.Through the expansion, core-container joint
Device 204 maintains to contact with reactor vessel 202.Meanwhile core-container joint device 204 maintains to contact and can with pumping 206
There is provided and axially align for pump 206.
Core-container joint device 204 provides carrying supporting (load-bearing supporting) for reactor core component 208.In such as figure
Shown, a part for reactor core component 208 is located in the chamber 211 limited by core-container joint device 204.Thus, core
Body-container joint device 204 also provides lateral support for reactor core component 208.
In the shown embodiment, core-container joint device 204 is always not necessarily that pump 206 provides generally vertical hold
Carry supporting.Alternatively, during operation, as container expands, 206 weight is pumped mainly by reactor lid 116 (in Fig. 1
In show) supporting.Core-container joint device 204 is limited for example due to possible generation during the seismic events of such as earthquake
The transverse shifting of pump 206 caused by vibrations.In some cases, pump 206 with core-container joint device 204 when engaging
It is totally constrained transverse shifting.In another embodiment, in design constraint, limited transverse shifting amount is possible.
The component of core-container joint device 204 is docked with the outlet of pump 206 to be directed so that pumping 206 effluent
Into reactor core component 208 or near.Usually, fluid passage 214 by pump 206 outlet and the row of usually pumping chamber
Go out a connection.Sodium is from wherein flowing through reactor core component 208 and flow into hot pond 104 (figure 1 illustrates).
The specific component of core-container joint device 204 is referred now to, exemplified attached bag includes base portion 210, pump guide assembly
212nd, fluid passage 214, pump guiding piece 215 and container joint portion 216.Other embodiments can include more or less component.
Base portion 210 provides supporting for reactor core component 208, is contacted with container 202, and support pump guide assembly
212.As shown in the figure, the outside of base portion 210 is about a truncated cone.However, other designs are possible, such as the base of cylinder
Portion 210.
Base portion 210 limits the core supporting arrangement 211 of supporting reactor core component 208.Pile component is reacted at one
Contemplate in situation, core supporting arrangement 211 drops in core-container joint device 204.By core supporting arrangement 211 with
Before core-container joint device 204 combines, reactor lid feature structure is alignd to realize proper alignment and Desired Height.
Core supporting arrangement 211 includes lateral support member 226 and vertical support part 228.Lateral support member 226 is substantially in ring
Shape and be sized such that reactor core component 208 be constrained to when in core supporting arrangement 211 without horizontal stroke
To movement.Vertical support part 228 supports the weight of reactor core component 208 and limits multiple openings as fluid passage
229.Opening 229 is arranged in a manner of grid.The size and dimension of opening 229 is according to their positions on vertical support part 228
And change.
Base portion 210 also limits multiple fluid passages.For example, fluid passage 222 is limited near the circumference of base portion 210.
In shown embodiment, two rows of fluid passages 222 are defined, wherein upper fluid passage 222 is less than lower fluid passage 222.Core-
Container joint device 204 further includes support grids 227.Support grids 227 include orthogonal and are orthogonal to the orientation of plate 248
Multiple supporting members.Flat backing member limits fluid passage 224.
Core-container joint device 204 is further included substantially at or near the intersection point of grid on vertical support part 228
Pad 240.Pad 240 contacts with reactor core support plate 248 and helps leveling reactor core component 208.One
In a embodiment, pad 240 and reactor core support plate 248 form stiff dough and slide docking.In an alternative embodiment, serve as a contrast
Pad 240 is docked with the recess in reactor core support plate 248.
Base portion 210 further includes container joint portion 216.In general, container joint portion 216 is designed that component to adjust
To adapt to the different heat expansion of interface arrangement.The foot --- basic ring 217 --- in container joint portion 216 is in its periphery and container
202 contacts.Basic ring 217 maintains to contact with container 202 when it is through expanded by heating.
In the shown embodiment, core-container joint device 204 includes two pump guide assembly 212, each pump 206 1
A pump guide assembly.However, depending on the quantity of pump 206 used in reactor, other embodiments can include more or less
Pump guide assembly 212.Pump guide assembly 212 is engaged with the discharge component of pump 206.
Usually, pump guide assembly 212 configures the opposite sides in base portion 210.In shown specific embodiment, pump draws
Guide assembly 212 is (separating 180 degree) directly opposite one another, this corresponds to the position of pump 206.
Pump guide assembly 212 and limit pump guiding piece 215.Pump guiding piece 215 and pump 206, the outlet pair particularly with pump 206
Connect.As most clearly visible in Fig. 3 and 4,206 end 236 is pumped in pump guiding piece 215 so that core-container joint dress
Putting 204 will not cause to separate relative to the vertically movable amount of the outlet of pump 206.It can match somebody with somebody between end 236 and pump guiding piece 215
It is equipped with gasket.
In the shown embodiment, pump guiding piece 215 includes axial part 230 and portion of terminal 232.In various embodiments,
Axial part 230 is double-walled to prevent a large amount of coolant loss in crack conditions.Portion of terminal 232 is used as collector (header) simultaneously
And including leading to the outlet of fluid passage 214.As shown in the figure, two fluid passages 214 extend from portion of terminal 232.In this example,
Single fluid passage 214 can be used, but may want to larger number so that fluid is more uniformly distributed near core component 208
Region.As shown in the figure, portion of terminal 232 is spherical in shape, but can be in other manifold shapes in other embodiments.For example, terminal
Portion 232 can be Y tube, but depending on the desired amt of distribution pipe, other shapes are possible.
In the shown embodiment, pump guide assembly 212 also limits window 218.Window 218 promotes sodium flowing and in the stream
The more uniform temperature of core-container joint device 204 during thermal transient in body, and window 218 reduce thermal mass and
Thermal stress.Fluid passage 214 extends through window 218 and is discharged at outlet 234 below reactor core component 208
In pumping chamber 245.
Core-container joint device 204 also accommodates one or more neutron guide-cans 231.Show four neutron guiding
Tank 231, but the neutron guide-can 231 of varying number can be used in other embodiments.
It is to be understood that the present disclosure is not limited to specific structure disclosed herein, processing step or material, but extend to association area
Skilled artisan will realize that their equivalent.It should also be understood that term used herein has merely for the sake of description
The purpose of body example, and be not intended to be limited.It must be noted that as used in the present specification, singulative
" one ", "one" and it is " described " include plural number reference, unless separately expressly stating otherwise within a context.
It is evident that system and method described herein be well suited for realizing the objects and advantages mentioned and
Wherein intrinsic objects and advantages.Those skilled in the art will recognize that the method and system in this specification can be used and permitted
Multimode is implemented and therefore should not be limited by the embodiment and example of foregoing illustrative.In this respect, different examples described herein
Any number of feature of son is combined into an example and with more than whole feature described herein or few feature
Alternate examples are possible.
Although describing various examples for the purpose of this utility model, various changes and modifications can be made, it is very
Well in the scope contemplated by the disclosure.Those skilled in the art, which can be made, will arbitrarily expect and covered in this
Many other changes in the spirit of utility model.
Claims (12)
- A kind of 1. core-container joint device, it is characterised in that including：Base portion, the base portion include being configured to the container joint portion contacted with reactor vessel；The first pump guide assembly being connected with the base portion, the first pump guide assembly, which limits, to be configured to and the first pump interface pair The the first pump guiding piece connect；Core supporting part, the core supporting part are limited by the base portion and are configured to receive a part for reactor core；WithThe described first pump guiding piece is in fluid communication with the core supporting part for fluid passage, the fluid passage.
- 2. core according to claim 1-container joint device, it is characterised in that the container joint portion includes basic ring.
- 3. core according to claim 1-container joint device, it is characterised in that the first pump guiding piece includes close Sealing, the seal are configured to accommodate axial movement of the first pump guiding piece relative to the described first pump.
- 4. core according to claim 3-container joint device, it is characterised in that the seal is located at the core Above supporting part.
- 5. core according to claim 1-container joint device, it is characterised in that further include：The second pump guide assembly being connected with base portion, the second pump guide assembly limit be configured to dock with the second pump second Pump guiding piece；WithThe described second pump guiding piece is in fluid communication with the core supporting part for second fluid passage, the second fluid passage.
- 6. core according to claim 5-container joint device, it is characterised in that the first pump guide assembly and institute State the opposite sides that the second pump guide assembly is located at the base portion.
- 7. core according to claim 1-container joint device, it is characterised in that the core supporting part is to described anti- Heap core is answered to provide both lateral support and vertical support.
- 8. core according to claim 1-container joint device, it is characterised in that the base portion, which limits, includes multiple streams The inner space of body passage.
- 9. core according to claim 1-container joint device, it is characterised in that the base portion has circular cone shape.
- 10. core according to claim 1-container joint device, it is characterised in that described first pumps guide assembly from institute State extending sideways for base portion.
- 11. core according to claim 1-container joint device, it is characterised in that the first pump guide assembly includes Pump guide assembly passage, the pump guide assembly passage has spherical portion and by the first pump discharge and reactor core component Outlet in the pumping chamber of lower section is in fluid communication.
- 12. core according to claim 11-container joint device, it is characterised in that the pump guide assembly passage bag Include two outlets and an entrance.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US201762512556P | 2017-05-30 | 2017-05-30 | |
| US62/512556 | 2017-05-30 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN207337936U true CN207337936U (en) | 2018-05-08 |
Family
ID=62425970
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201720778972.2U Expired - Fee Related CN207337936U (en) | 2017-05-30 | 2017-06-30 | Core-container joint device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN207337936U (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113990533A (en) * | 2021-10-22 | 2022-01-28 | 中国原子能科学研究院 | Reactor and coolant conveying structure thereof |
-
2017
- 2017-06-30 CN CN201720778972.2U patent/CN207337936U/en not_active Expired - Fee Related
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113990533A (en) * | 2021-10-22 | 2022-01-28 | 中国原子能科学研究院 | Reactor and coolant conveying structure thereof |
| CN113990533B (en) * | 2021-10-22 | 2024-05-10 | 中国原子能科学研究院 | Reactor and coolant conveying structure thereof |
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Granted publication date: 20180508 |