CN107516550A - Reactor lid - Google Patents
Reactor lid Download PDFInfo
- Publication number
- CN107516550A CN107516550A CN201611256316.2A CN201611256316A CN107516550A CN 107516550 A CN107516550 A CN 107516550A CN 201611256316 A CN201611256316 A CN 201611256316A CN 107516550 A CN107516550 A CN 107516550A
- Authority
- CN
- China
- Prior art keywords
- heat exchanger
- pair
- tubular container
- port
- pump case
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 239000000446 fuel Substances 0.000 claims description 34
- 238000012546 transfer Methods 0.000 claims description 13
- 238000012545 processing Methods 0.000 claims description 12
- 239000002826 coolant Substances 0.000 description 42
- 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 27
- 229910052708 sodium Inorganic materials 0.000 description 27
- 239000011734 sodium Substances 0.000 description 27
- 238000006243 chemical reaction Methods 0.000 description 11
- 102000005393 Sodium-Potassium-Exchanging ATPase Human genes 0.000 description 10
- 108010006431 Sodium-Potassium-Exchanging ATPase Proteins 0.000 description 10
- 239000007789 gas Substances 0.000 description 9
- 238000013213 extrapolation Methods 0.000 description 6
- 238000002485 combustion reaction Methods 0.000 description 5
- 238000005516 engineering process Methods 0.000 description 4
- 239000007788 liquid Substances 0.000 description 4
- 230000004992 fission Effects 0.000 description 3
- 238000012544 monitoring process Methods 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
- 238000001816 cooling Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000005611 electricity Effects 0.000 description 2
- 230000013011 mating Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 230000003068 static 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
- 241000196324 Embryophyta Species 0.000 description 1
- 240000007594 Oryza sativa Species 0.000 description 1
- 235000007164 Oryza sativa Nutrition 0.000 description 1
- 229910052776 Thorium Inorganic materials 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 229910052786 argon Inorganic materials 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 230000008030 elimination Effects 0.000 description 1
- 238000003379 elimination reaction Methods 0.000 description 1
- 238000010304 firing Methods 0.000 description 1
- 238000011065 in-situ storage Methods 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 230000001788 irregular Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000002139 neutron reflectometry Methods 0.000 description 1
- 238000005025 nuclear technology Methods 0.000 description 1
- 239000003507 refrigerant Substances 0.000 description 1
- 235000009566 rice Nutrition 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/22—Structural association of coolant tubes with headers
-
- 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
- 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 present invention relates to a kind of reactor lid, and it has bullet assembly, and the bullet assembly has circular cross-section.Reactor lid is included datum diameter that bullet assembly and reactor lid are divided equally, the first pump case, the second pump case relatively positioned on datum diameter and first pump case and first pair of heat exchanger tubular container.First pair of heat exchanger tubular container is positioned to adjacent with the first pump case and is positioned at its opposite sides.Second pair of heat exchanger tubular container relatively positions on datum diameter and first pair of direct heat exchanger tubular container.Each in first pair of direct heat exchanger tubular container configures the opposite sides in the first pump case and configured between one in the first pump case and first pair of direct heat exchanger tubular container.Second pair of direct heat exchanger tubular container relatively positions on datum diameter and first pair of direct heat exchanger tubular container.
Description
Technical field
The application is related to nuclear technology field, more particularly to a kind of reactor lid.
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, the light-water reactor fuel of consumption or thorium after starting as heavily loaded fuel indefinite duration
The reactor that the ripple that ground operates and wherein breeds and then burn will be advanced relative to fuel.Therefore, in some respects, TWR
Propagation is to rely on to upstate and the through type fast reaction heap of the subcritical heavily loaded operating fuel of combustion in situ.In TWR
In, moved in the central core of propagation and fission ripple (" propagation-combustion wave ") originating from reactor and relative to fuel.Firing
Expect it is static in the case of, propagation and combustion wave from ignition point to external expansion.In some cases, fuel is moveable so as to breed
Moved with combustion wave relative to core static (for example, standing wave) but relative to fuel；Standing wave should be considered as a kind of TWR.Fuel stack
The movement of part is referred to as " fuel exchange (fuel shuffling) " and can complete standing wave, and this is (hot, logical to reactor characteristic
Amount, power, fuel combustion etc.) regulation.Fuel assembly is switched in central core, and central core is configured in reactor vessel
In.Fuel assembly includes fission nuclear fuel component and can breed nuclear fuel assembly.It may also be configured with central core for adjusting
Save the reaction controlling component of reactor characteristic.
The fission energy limited by standing wave forms heat energy, and heat energy is successively through one or more Main Coolant loops and centre
Coolant loop is transplanted on steam generator to generate electricity, and repels Low Temperature Thermal by one group of water-cooled vacuum condenser.Cooling
Agent system, which is divided into Main Coolant loop and intercoolant loop, to be helped to maintain core and the integrality of Main Coolant loop.
In TWR, Main Coolant loop and intercoolant loop are both using Liquid Sodium as cooling agent.
The content of the invention
On the one hand, the technology is related to a kind of reactor lid, and it includes：It is centrally positioned on the reactor lid
Bullet assembly, wherein the bullet assembly has a circular cross-section, and wherein described reactor lid has and divides described insert equally
Plug assembly and the datum diameter for dividing the reactor lid equally；First pump case；Second pump case, second pump case are closed
Relatively positioned in the datum diameter and first pump case；First pair of heat exchanger tubular container, wherein described first pair
Heat exchanger tubular container is positioned to adjacent with first pump case and is located at its opposite sides；Second pair of heat exchanger tube capacity
Device, wherein second pair of heat exchanger tubular container is relative with first pair of heat exchanger tubular container on the datum diameter
Ground positions；First pair of direct heat exchanger tubular container, wherein each in first pair of direct heat exchanger tubular container
Configure the opposite sides in first pump case and configure in first pump case and first pair of direct heat exchange
Between one in device tubular container；Second pair of direct heat exchanger tubular container, second pair of direct heat exchanger tubular container close
Relatively positioned in the datum diameter and first pair of direct heat exchanger tubular container.In one embodiment, it is described anti-
Heap top cover is answered also to include fuel transfer port, wherein the fuel transfers port locations into the outer rim neighbour with the bullet assembly
Connect.In another embodiment, the fuel transfers port locations on the datum diameter.In another embodiment, described
In one pump case, second pump case, first pair of heat exchanger tubular container and second pair of heat exchanger tubular container
Each geometric center formed hexagon one group of summit.In another embodiment, the reactor lid includes master
Fuel treatment port；Port is handled with main blanketing gas, wherein the main blanketing gas handles port on the datum diameter
Relatively positioned with main fuel processing port.In another embodiment, the main fuel processing port is positioned approximately in institute
State between one in first pair of heat exchanger tubular container and one in second pair of heat exchanger tubular container.
Brief description of the drawings
Below form the application a part accompanying drawing be for described technology it is illustrative and be not intended to
Any mode limits the scope for the technology for requiring patent right, and the scope should be based on claim appended herein.
Fig. 1 shows to melt some basic building blocks of fuel reaction heap in form of a block diagram.
Fig. 2 is the top plan view of exemplary reaction heap top cover, shows connected multiple components.
Fig. 3 A are the fragmentary top plan views of the exemplary reaction heap top cover shown in Fig. 2.
Fig. 3 B are the fragmentary top plan views of the exemplary reaction heap top cover shown in Fig. 2.
Embodiment
Fig. 1 shows some basic building blocks of traveling wave heap (TWR) 100 in form of a block diagram.In general, TRW100 includes accommodating
The reactor core 102 of multiple fuel assembly (not shown).Core 102, which configures, is keeping the Liquid Sodium cooling agent of certain volume
Its lowest position in 106 pond 104.Pond 104 is referred to as hot pond and with than also accommodating around Liquid Sodium cooling agent 106
The high sodium temperature of cold drop 108 (being attributed to the energy as caused by the fuel assembly in reactor core 102).Hot pond 104 is by interior
Portion's container 110 separates with cold drop 108.The head space 112 of the ullage of sodium cooling agent 106 can be filled with the lazy of such as argon gas
Property blanketing gas.Safety container 114 surrounds reactor core 102, hot pond 104 and cold drop 108, and utilizes reactor lid
116 sealings.Reactor lid 116 provides the various inlet points led in the inside of safety container 114.
The size of reactor core 102 is selected based on Multiple factors, including the characteristic of fuel, desired generated energy, can
Space of reactor 100 of acquisition etc..TWR various embodiments as needed or can it is expected to be used for low-power (about 300MWe- about
500MWe), middle power (about 500MWe- about 1000MWe) and high-power (about 1000MWeMore than and) application in.Can be by core
The surrounding of the heart 102 sets unshowned one or more reflectors to return to neutron reflection in core 102 to improve reactor 100
Performance.
Sodium cooling agent 106 circulates via main sodium cooling agent pump 118 in container 114.Main coolant pump 118 is from cold drop 108
Aspirate sodium cooling agent 106 and press close to reactor core (for example, thereunder) and it is ejected into hot pond 104, cool down herein
Agent 106 is heated due to the reaction occurred in reactor core 102.The heated cooling agent 106 of a part is from hot pond 104
Top enters intermediate heat exchanger 120, and the opening position in cold drop 108 leaves intermediate heat exchanger 120.This main cooling
Agent loop 122 thus makes sodium cooling agent 106 be circulated completely in reactor vessel 114.
Intermediate heat exchanger 120 also includes Liquid Sodium cooling agent and as Main Coolant loop 122 and electricity generation system 123
Between barrier, thus ensuring that core 102 and the integrality of Main Coolant loop 122.Intermediate heat exchanger 120 is by warm from master
Coolant loop 122 (being fully accommodated in container 114) is delivered to intercoolant loop 124 and (is positioned only part container 114
It is interior).Intermediate heat exchanger 120 passes through the opening in inner pressurd vessel 110, so as to bridge hot pond 104 and cold drop 108 (to allow to lead
Sodium 106 in coolant loop 122 flows therebetween).In one embodiment, four intermediate heat exchangers 120 are distributed in appearance
In device 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 transferred 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 separates with the sodium cooling agent 126 of intercoolant loop 124, while transferring heat energy therebetween.
Direct heat exchanger 132 stretches into hot pond 104 and the sodium cooling agent 106 into Main Coolant loop 122 provides
Extra cooling.Direct heat exchanger 132 is configured to allow for sodium cooling agent 106 to enter and leave heat exchanger from hot pond 104
132.Direct heat exchanger 132 has the structure similar to intermediate heat exchanger 120, and its middle pipe 134 keeps Main Coolant loop
122 sodium cooling agent 106 separates with the sodium cooling agent 136 of direct reactor coolant loop 138, while transmits heat therebetween
Energy.
Other assisted reaction pile elements include but is not limited to (in reactor vessel 114 and outside reactor vessel 114)
It is not shown but will become apparent to pump, check-valves, stop valve, flange, drain tank etc. to those skilled in the art.Do not show
Go out through reactor head 116 other through hole (for example, for the port of main refrigerant pump 118, inert blanketing gases and
Check port, sodium processing port etc.).Control system 140 is used for the various components for controlling and monitoring reactor 100.
Broadly, the present disclosure describes the configuration for the performance for improving the reactor 100 described in Fig. 1.Specifically, reactor
Embodiment, configuration and the arrangement of top cover 116 are illustrated and more specifically described below with reference to Fig. 2-3B.
Fig. 2 is the top plan view of an exemplary embodiment of reactor lid 200.Reactor lid 200 includes outer
Annular region 202 and bullet assembly 203, the bullet assembly include extrapolation plug assembly 204 and interior bullet assembly 206.In general,
Reactor head 200 supports the weight of pump and other components, and provides the port for the inside for being available for reaching reactor vessel.If
The port put in reactor lid 200 is shown in Fig. 3 A and 3B discussed in further detail below.Fig. 2 is shown at these ends
Various components (for example, housing, container etc.) on the top of mouth.The other embodiments of reactor lid 200 may include quantity ratio
More than embodiment shown in Fig. 2-3B or few component and port, and its different configuration and arrangement.
Reactor lid 200 has circular cross-section and the e.g., from about depth of 2-4 rice.Reactor lid 200 is in reaction core
Side is located so that the central vertical axis of reactor lid 200 and the central vertical axis of reactor core are substantially right in the heart
Together.Reactor lid annular region 202 supports various components, including but not limited to primary sodium pump housing 210, intermediate heat exchanger pipe
Container 212, direct heat exchanger tubular container 214 and one or more fuel transfer port 216.Other components include main covering gas
Body processing system pipe container 218, main sodium processing system pipe container 220, check port 224 and main blanketing gas and monitoring
Port 226.As used herein, term " container " description is at the port of reactor lid 200 or pipeline or near it
Any housing or container enclosed is provided.Typically, container configuration is turned to curved through the pipeline of reactor lid 200 in pipeline
Around head.Single fuel transfer port 216 is located so that the outer of the periphery of fuel transfer port 216 and extrapolation plug assembly 204
Week is adjacent and tangent or close to tangent with its.Port 216 is transferred by positioning fuel as described above, the port can be easier to pass through
Reached by the component in container.In certain embodiments, reactor lid annular region 202 accommodates main blanketing gas in addition
Processing system filling piping 222 and additional main sodium processing pipe container 221.
Pipeline from intermediate heat exchanger tubular container 212 and direct heat exchanger tubular container 214 is illustrated to be parallel to each other
Ground and perpendicular to reactor lid 200 and bullet assembly 203 are divided equally datum diameter D (being shown in Fig. 3 A and 3B) extension.
In further embodiments, this alignment alterable of pipeline, size and dimension requirement and reaction depending on reactor plant
The position that heap core 102 is located at.Extrapolation plug assembly 204 can surround to be rotated with the axis identical axis of reactor head 200.Solely
Extrapolation plug assembly 204 is stood on, interior bullet assembly 206 is also rotatable.The rotation axis of interior bullet assembly 206 deviate and parallel to
The rotation axis of extrapolation plug assembly 204.
Fig. 3 A and 3B are the first half portion and the second half portion of the top plan view on reactor head 200 respectively.Fig. 3 A and 3B
The port limited by reactor lid annular region 202, and the mating surface for the component related to each port are shown.
In some embodiments, mating surface may include base or flange.The each port limited by reactor lid annular region 202
With circular cross-section, it is contemplated that other shapes.The subsidiary component shown in fig 1 and 2 not shown in Fig. 3 A and 3B, but this
The port that a little components can be associated with is substantially aligned or connects.Fig. 3 A and 3B are discussed in the lump below.Other reactor heads are real
Applying example may include the more or less component of quantity and/or port.
As shown in figs.3 a and 3b, arrange the port symmetrical in reactor lid annular region 202.End in Fig. 3 A and 3B
The label of mouth is generally corresponding with the label above with respect to the associated components described in Fig. 2.As illustrated, datum diameter D provides use
The axis of symmetry of many ports in reactor lid 200.For example, primary sodium pump port 310, intermediate heat exchanger port 312,
Direct heat exchanger port 314 and inspection port 224 are symmetrically arranged at datum diameter D opposite sides.For Main Coolant
The primary sodium pump housing 210 of pump 118 can be connected with the flange around primary sodium pump port 310.Main sodium cooling agent pump 118 can be through primary sodium pump
Housing 210 reaches.Intermediate heat exchanger tubular container 216 can be connected with the flange around intermediate heat exchanger port 312.Into with
The pipeline for leaving intermediate heat exchanger tubular container 216 forms a part for intercoolant loop 126.Direct heat exchanger tube capacity
Device 214 surrounds the pipeline for making cooling agent circulation in direct heat exchanger 132.Direct heat transfer tubular container 214 also can be with direct warm
Flange connection around exchanger port 314.
The configuration of the geometric center of primary sodium pump port 310 and intermediate heat exchanger port 312 is being collectively forming the line of six face shapes
Apex.These lines are illustrated as line H1 and H2.In various embodiments, hexagon can be isogonism, equilateral, rule
Then, or the hexagon can be irregular.Line H1 corresponds to primary sodium pump port 310 and adjacent intermediate heat exchanger port
The distance between 312 geometric center.Line H1 need not have with extending between the geometric center of intermediate heat exchanger port 312
The equal length of line H2.Online in the H1 length example equal with line H2, this will symbol primary sodium pump port 310 and intermediate heat
The regular hexagonal configuration of exchanger port 312.Being arranged symmetrically for the various ports of datum diameter D either side helps to improve
Flowing of the cooling agent in container and the inflow into container, so as to improve operating efficiency, improve heat transfer, elimination focus etc..
Each in four direct heat exchanger ports 314 be positioned at one in primary sodium pump port 310 with it is adjacent
Intermediate heat exchanger port 312 between.Although fuel transfer port 216 is shown as by reactor lid in figures 3 a and 3b
200 datum diameter D deciles, but it is contemplated that other positions.In addition, as shown in figs.3 a and 3b, fuel transfers the edge of port 216
It is not tangent with the edge of outer plug 304.This is attributable to supporting member and other components in the circumference of extrapolation plug assembly 204.This
A little supporting members are illustrated in fig. 2, but are not shown in figures 3 a and 3b.
Monitoring port 226 be located at reactor lid 200 to quadrant (quadrant) in because these quadrants by
Both datum diameter D and diameter Dp perpendicular to datum diameter D are limited.With multiple main sodium processing system ports 321 and master
In the embodiment of blanketing gas processing system port 322, these ports also be located to quadrant in.
It should be understood that the disclosure is not limited to specific structure, processing step or material disclosed herein, 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 embodiment, and be not intended to be limited.It must be noted that as used in this manual, singulative
" one ", "one" includes plural reference with " described ", 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 limited by the embodiment and example of foregoing illustrative.In this respect, it is described herein different real
Any number of feature for applying example is combined into one embodiment and with more than whole features described herein or few spy
The alternate embodiment of sign is possible.
Although describing various embodiments for the purpose of this disclosure, various changes and modifications can be made, its is fine
Ground is in the scope contemplated by the disclosure.Those skilled in the art, which can be made, will arbitrarily expect and covered in this public affairs
Many other changes in the spirit opened.
Claims (6)
1. a kind of reactor lid, including：
The bullet assembly being centrally positioned on the reactor lid, wherein the bullet assembly has circular cross-section, and
Wherein described reactor lid includes dividing the bullet assembly equally and divides the datum diameter of the reactor lid equally；
First pump case；
Second pump case, second pump case relatively position on the datum diameter and first pump case；
First pair of heat exchanger tubular container, wherein first pair of heat exchanger tubular container is positioned to adjacent with first pump case
Connect and be located at the opposite sides of first pump case；
Second pair of heat exchanger tubular container, wherein second pair of heat exchanger tubular container is on the datum diameter and described the
A pair of heat exchanger tubular containers relatively position；
First pair of direct heat exchanger tubular container, wherein, each in first pair of direct heat exchanger tubular container is matched somebody with somebody
Put the opposite sides in first pump case and configure in first tube shell and first pair of direct heat exchanger
Between one in tubular container；With
Second pair of direct heat exchanger tubular container, second pair of direct heat exchanger tubular container is on the datum diameter and institute
First pair of direct heat exchanger tubular container is stated relatively to position.
2. reactor lid according to claim 1, in addition to：
Fuel transfers port, is abutted wherein the fuel transfers port locations into the outer rim of the bullet assembly.
3. reactor lid according to claim 2, wherein, the fuel transfers port locations in the datum diameter
On.
4. reactor lid according to claim 1, wherein, first pump case, second pump case, described
The geometric center of each of a pair of heat exchanger tubular containers and second pair of heat exchanger tubular container forms hexagon
One group of summit.
5. reactor lid according to claim 1, in addition to：
Main fuel handles port；With
Main blanketing gas handles port, wherein the main blanketing gas handles port on the datum diameter and the main fuel
Processing port relatively positions.
6. reactor lid according to claim 5, wherein, the main fuel processing port is positioned approximately in described first
To between one in one in heat exchanger tubular container and second pair of heat exchanger tubular container.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US201662351201P | 2016-06-16 | 2016-06-16 | |
| US62/351201 | 2016-06-16 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN107516550A true CN107516550A (en) | 2017-12-26 |
Family
ID=60607301
Family Applications (2)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201611256316.2A Pending CN107516550A (en) | 2016-06-16 | 2016-12-30 | Reactor lid |
| CN201621477092.3U Active CN206758138U (en) | 2016-06-16 | 2016-12-30 | Reactor lid |
Family Applications After (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201621477092.3U Active CN206758138U (en) | 2016-06-16 | 2016-12-30 | Reactor lid |
Country Status (1)
| Country | Link |
|---|---|
| CN (2) | CN107516550A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107516550A (en) * | 2016-06-16 | 2017-12-26 | 泰拉能源有限责任公司 | Reactor lid |
Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3847733A (en) * | 1970-08-05 | 1974-11-12 | E Ventre | Nuclear reactor with integrated heat exchanger |
| JPH01242997A (en) * | 1988-03-24 | 1989-09-27 | Toshiba Corp | Fast breeder |
| JPH0267995A (en) * | 1988-09-02 | 1990-03-07 | Hitachi Ltd | Fuelling equipment of fast breeder reactor |
| CN1069596A (en) * | 1991-08-20 | 1993-03-03 | 法玛通公司 | The inner structure of fast neutron nuclear reaction heap |
| US20080310575A1 (en) * | 2005-09-21 | 2008-12-18 | Luciano Cinotti | Nuclear Reactor, In Particular a Liquid-Metal-Cooled Nuclear Reactor |
| CN102282625A (en) * | 2008-11-19 | 2011-12-14 | 原子能与替代能源署 | Sfr nuclear reactor of the integrated type with improved convection operation |
| CN103238186A (en) * | 2010-10-04 | 2013-08-07 | 原子能和替代能源委员会 | Integrated sodium-cooled fast nuclear reactor |
| CN104575635A (en) * | 2014-12-12 | 2015-04-29 | 中国原子能科学研究院 | Accident decay heat discharge system for non-symmetric distribution of large pool type sodium-cooled fast reactors |
| JP2015158471A (en) * | 2014-02-25 | 2015-09-03 | 株式会社東芝 | Fuel exchange system and nuclear reactor system |
| CN206758138U (en) * | 2016-06-16 | 2017-12-15 | 泰拉能源有限责任公司 | Reactor lid |
-
2016
- 2016-12-30 CN CN201611256316.2A patent/CN107516550A/en active Pending
- 2016-12-30 CN CN201621477092.3U patent/CN206758138U/en active Active
Patent Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3847733A (en) * | 1970-08-05 | 1974-11-12 | E Ventre | Nuclear reactor with integrated heat exchanger |
| JPH01242997A (en) * | 1988-03-24 | 1989-09-27 | Toshiba Corp | Fast breeder |
| JPH0267995A (en) * | 1988-09-02 | 1990-03-07 | Hitachi Ltd | Fuelling equipment of fast breeder reactor |
| CN1069596A (en) * | 1991-08-20 | 1993-03-03 | 法玛通公司 | The inner structure of fast neutron nuclear reaction heap |
| US20080310575A1 (en) * | 2005-09-21 | 2008-12-18 | Luciano Cinotti | Nuclear Reactor, In Particular a Liquid-Metal-Cooled Nuclear Reactor |
| CN102282625A (en) * | 2008-11-19 | 2011-12-14 | 原子能与替代能源署 | Sfr nuclear reactor of the integrated type with improved convection operation |
| CN103238186A (en) * | 2010-10-04 | 2013-08-07 | 原子能和替代能源委员会 | Integrated sodium-cooled fast nuclear reactor |
| JP2015158471A (en) * | 2014-02-25 | 2015-09-03 | 株式会社東芝 | Fuel exchange system and nuclear reactor system |
| CN104575635A (en) * | 2014-12-12 | 2015-04-29 | 中国原子能科学研究院 | Accident decay heat discharge system for non-symmetric distribution of large pool type sodium-cooled fast reactors |
| CN206758138U (en) * | 2016-06-16 | 2017-12-15 | 泰拉能源有限责任公司 | Reactor lid |
Also Published As
| Publication number | Publication date |
|---|---|
| CN206758138U (en) | 2017-12-15 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN108417277B (en) | Integrated reactor body system and chloride reactor system | |
| EP3301683B1 (en) | A pressure-tube nuclear reactor with a low pressure moderator and fuel channel assembly | |
| CN108399957B (en) | Small-size modularization flows ball bed villaumite cooling high temperature reactor | |
| CN207038184U (en) | Rod steerable system in container | |
| CN202615805U (en) | Non-dynamic safety case cooling system | |
| CN206758138U (en) | Reactor lid | |
| JP2007271157A (en) | Support structure for heat transfer tube | |
| CN109256222A (en) | The cold fast neutron nuclear reaction shut-down system of sodium | |
| CN207038180U (en) | Nuclear energy production facility | |
| CN114651311A (en) | Molten fuel reactor and annular ring plate for molten fuel reactor | |
| CN104662613A (en) | Lower end plug with temperature reduction device and nuclear reactor fuel rod including same | |
| CN206726783U (en) | Internal container for reactor | |
| CN206558223U (en) | Catheter body | |
| CN207337935U (en) | Core component and core constrained system | |
| CN209310076U (en) | A kind of UTILIZATION OF VESIDUAL HEAT IN cooker racks and residual heat using device | |
| EP2814039B1 (en) | Water supply pipe for steam generator | |
| CN207038181U (en) | Core body container joint device | |
| CN207038191U (en) | Core component inlet nozzle | |
| CN109830313A (en) | A kind of steam generator spiral heat exchange tube support construction that welding is just dismantled | |
| CN207038187U (en) | Cable management system | |
| CN115527696B (en) | Tandem high-temperature gas cooled reactor nuclear energy system and operation method thereof | |
| CN108518663B (en) | A kind of steam generator and nuclear equipment suitable for lead bismuth heap | |
| CN213815566U (en) | Microchannel heat exchanger container, high-temperature gas cooled reactor using same and system | |
| CN206697240U (en) | Nuclear energy production facility | |
| CN115985526A (en) | Heat pipe type fuel element, reactor core, operation method and application thereof |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| WD01 | Invention patent application deemed withdrawn after publication | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20171226 |