CN207038183U - Reactor system - Google Patents
Reactor system Download PDFInfo
- Publication number
- CN207038183U CN207038183U CN201720697359.8U CN201720697359U CN207038183U CN 207038183 U CN207038183 U CN 207038183U CN 201720697359 U CN201720697359 U CN 201720697359U CN 207038183 U CN207038183 U CN 207038183U
- Authority
- CN
- China
- Prior art keywords
- reactor
- heat exchanger
- lid
- intermediate heat
- sodium
- 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
- 229910052708 sodium Inorganic materials 0.000 claims abstract description 72
- 239000011734 sodium Substances 0.000 claims abstract description 72
- 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 claims abstract description 71
- 238000012545 processing Methods 0.000 claims abstract description 31
- 230000000306 recurrent effect Effects 0.000 claims abstract description 15
- 229910000831 Steel Inorganic materials 0.000 claims description 9
- 238000001816 cooling Methods 0.000 claims description 9
- 239000010959 steel Substances 0.000 claims description 9
- 239000002826 coolant Substances 0.000 description 39
- 239000000446 fuel Substances 0.000 description 16
- 238000006243 chemical reaction Methods 0.000 description 10
- 238000002485 combustion reaction Methods 0.000 description 6
- 239000007788 liquid Substances 0.000 description 6
- 229910052792 caesium Inorganic materials 0.000 description 4
- TVFDJXOCXUVLDH-UHFFFAOYSA-N caesium atom Chemical compound [Cs] TVFDJXOCXUVLDH-UHFFFAOYSA-N 0.000 description 4
- 238000005516 engineering process Methods 0.000 description 4
- 230000004992 fission Effects 0.000 description 4
- 239000007789 gas Substances 0.000 description 4
- 239000000463 material Substances 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 239000003758 nuclear fuel Substances 0.000 description 3
- 229910001220 stainless steel Inorganic materials 0.000 description 3
- 239000010935 stainless steel Substances 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 230000008859 change Effects 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000005611 electricity Effects 0.000 description 2
- 238000002156 mixing Methods 0.000 description 2
- 230000000149 penetrating effect Effects 0.000 description 2
- 230000001681 protective effect Effects 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
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-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
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 230000004913 activation Effects 0.000 description 1
- 229910052786 argon Inorganic materials 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 239000000110 cooling liquid Substances 0.000 description 1
- 230000005496 eutectics 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
- 230000007774 longterm Effects 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 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
- 238000003825 pressing Methods 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 239000003507 refrigerant Substances 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
- 238000003466 welding Methods 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
A kind of reactor system is the utility model is related to, the reactor system has reactor vessel, and the reactor vessel has reactor lid of the configuration on reactor vessel.Main sodium processing system supply pipe and recurrent canal penetrate reactor lid.The distance that supply pipe extends below reactor lid is more than the distance that recurrent canal extends below reactor lid.
Description
Technical field
It the utility model is related to nuclear reaction field, more particularly to a kind of reactor system.
Background technology
Fission-type reactor includes propagation-burning fast reaction heap (also referred to as traveling wave reactor, or TWR).TWR refer to by
Be designed to use after starting weary light-water reactor fuel after natural uranium, depleted uranium or reprocessing as heavily loaded fuel without
Operate time limit and wherein breed and with the reactor that will be advanced relative to fuel of ripple of after-combustion.Therefore, in some respects,
TWR is to rely on propagation to upstate and the through type fast reaction heap of the subcritical heavily loaded operating fuel of combustion in situ.
In TWR, moved in the central core of propagation and fission ripple (" propagation-combustion wave ") originating from reactor and relative to fuel.
In the case where fuel is static, propagation and combustion wave are from burning-point to external expansion.In some cases, fuel is moveable so as to increase
Grow with combustion wave relative to core body static (for example, standing wave) but moved relative to fuel；Standing wave should be considered as a kind of TWR.Fuel
The movement of component 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.The central core that wherein fuel assembly is switched is configured in reactor vessel.Fuel
Component includes fission nuclear fuel component and can produce the nuclear fuel assembly of fissile material.The generally centrally located core of reaction controlling component
For regulation reactor characteristic in body.
The fission energy limited by standing wave forms heat energy, and the heat 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 body 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 reactor system is the utility model is related to, the reactor system includes：Reactor vessel；Instead
Heap top cover is answered, the reactor lid is configured on reactor vessel；Returned with main sodium processing system supply pipe and main sodium processing system
Return pipe, wherein each of main sodium processing system supply pipe and main sodium processing system recurrent canal all penetrate reactor lid, and
And the length extended below reactor lid of wherein main sodium processing system supply pipe exists than main sodium processing system recurrent canal
The length length of extension below reactor lid.In one example, the reactor system have configuration in reactor vessel and
Direct heat exchanger below reactor lid, the wherein direct heat exchanger include configuring below reactor lid
Entrance and exit, and the wherein entrance of direct heat exchanger is located at below reactor lid and is more than main sodium processing system supply pipe
The length extended below reactor lid distance at.In another example, the reactor system includes：Configuration is being reacted
Heap container and the intermediate heat exchanger below reactor lid, the wherein intermediate heat exchanger include configuring in reactor
Entrance and exit below top cover, and wherein the entrance of intermediate heat exchanger is located at below reactor lid than direct heat exchange
At the big distance of the distance below reactor lid of the entrance of device.In another example, the reactor system includes penetrating
A pair of direct reactor cooling tubes that reactor lid and the opening position in reactor vessel are connected with direct heat exchanger.
In yet another example, the reactor system includes penetrating reactor lid and the opening position in reactor vessel and centre
A pair of intermediate heat delivery pipes of heat exchanger connection.
In another example of above-mentioned aspect, the outlet of direct heat exchanger is located at the ratio intermediate heat below reactor lid
The entrance of exchanger is located at the big distance of the distance below reactor lid.In one example, intermediate heat exchanger includes
Four intermediate heat exchangers.In another example, it is (interior also to include boss portion of the configuration in reactor vessel for the reactor system
Portion's container/redan, redan), wherein at least a portion of intermediate heat exchanger is configured below the boss portion.In another example
In son, intermediate heat exchanger is coated with boronated steel at least in part.In yet another example, the diameter of intermediate heat exchanger it is big
About half is wrapped by.In another example, only part of the configuration of intermediate heat exchanger above boss portion is coated with boronated steel.
Brief description of the drawings
Forming a part of accompanying drawing of the present 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, the scope should be based on claim appended herein.
Fig. 1 shows some basic building blocks of traveling wave reactor in form of a block diagram.
Fig. 2 is the partial side sectioned view of traveling wave reactor.
Embodiment
Fig. 1 shows some basic building blocks of traveling wave reactor (TWR) 100 in form of a block diagram.In general, TRW100 includes
Accommodate the reactor core body 102 of multiple fuel assembly (not shown).Core body 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 by energy caused by the fuel assembly in reactor core body 102).Hot pond 104 passes through boss portion 110
Separated with cold drop 108.The headroom 112 of the ullage of sodium cooling agent 106 is filled with the inert protective gas of such as argon gas.
Reactor vessel 114 surrounds reactor core body 102, hot pond 104 and cold drop 108, and is sealed using reactor lid 116.Instead
Heap top cover 116 is answered to provide the various maintenance points led in the inside of reactor vessel 114.
The size of reactor core body 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 examples 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) application in.Can be by core body
102 surroundings set unshowned one or more reflectors to return to neutron reflection in core body 102 to improve reactor 100
Performance.In addition, can produce fissile material and fissible nuclear component moves (or " switching ") to control in core body 102 and around it
Make the nuclear reaction wherein occurred.
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 it is ejected into pumping chamber (plenum) below reactor core body 102.The quilt of cooling agent 106
Drive upwardly through core body and be heated due to the reaction occurred in reactor core body 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 sodium cooling agent 106 is circulated completely in reactor vessel 114.
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
Boss portion 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.Or 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 separates 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 generally 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
Direct heat exchanger cooling agent sodium-potassium eutectic of the sodium of Main Coolant loop 122 and direct reactor coolant loop 138
(NaK) 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, be check-valves, stop 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 port and protective gas port etc.) it is not shown.Control system 140 is used to controlling and monitoring composition
The various components and system of reactor 100.
Broadly, the utility model describes the configuration for the performance for improving the reactor 100 described in Fig. 1.Specifically, it is hot
Example, configuration and the arrangement of exchanger and be used in processing sodium cooling agent circulation pipe be illustrated and below with reference to
Fig. 2 is more fully described.
Fig. 2 is the partial side sectioned view of traveling wave reactor 200.Reactor 200 includes reactor vessel 202 and with close
Envelope reactor 200 and provide for managing, the reactor lid 204 of the through hole of sensor and other components is top.Thermodynamic barrier
206 configurations are below reactor lid 204 and are configured with through hole to allow multiple pipes or other components to pass through.Main sodium
Processing system 300 is located remotely from reactor vessel 202 and the fission product for removing such as caesium from sodium cooling agent.Main sodium
Processing system 300 makes the sodium from the suction of hot pond 208 cycle through one or more caesium collectors and then makes the sodium after processing
Cooling agent returns to hot pond 208.Therefore, main sodium processing system 300 is anti-using extending below reactor lid 204 and extending into
Answer two or more pipes of the inside of heap container 202.
Main sodium processing system supply pipe 210 is illustrated in fig. 2 together with main sodium processing system recurrent canal 212.Supply
Pipe 210 and recurrent canal 212 are shown as each other pressing close in reactor vessel 202, but should typically be arranged to limitation processing
Sodium afterwards is returned in supply pipe 210 from the short circuit of recurrent canal 212.It is contemplated that a variety of such configurations for preventing short circuit.
In one example, supply pipe 210 and recurrent canal 212 can be located at the relative or substantially relative both sides of reactor vessel (for example, radially
Ground is separately up to about 180 °).
In another example, as shown in Fig. 2 supply pipe 210 and recurrent canal 212 closely configure each other, but with difference
Length (thus extending different distance below reactor lid 204).As illustrated, recurrent canal 212 terminates at basal plane --- this
It is the bottom surface 214 of reactor lid 204 in the case of kind --- at the first distance D1 of lower section.Supply pipe 210 is terminated under basal plane
At the second distance D2 of side.Therefore, supply pipe 210 is taken out from the inside of reactor vessel 202 --- specifically hot pond 208 ---
Sodium is inhaled, and it is transported to caesium collector to be handled.After the treatment, the sodium after relatively cold processing then via
Recurrent canal 212 is delivered back into hot pond 208.Sodium after the colder, processing is later fallen into hot pond, and then it is heated to heat
The temperature in pond 208, thus strengthen the Natural Circulation in hot pond 208 and mixing.The heating of sodium is due in reactor vessel 202
(specifically, in core body 216) occur nuclear reaction and occur.
Main sodium processing system 300 is by high capacity pump (for example, the siphon from reactor vessel 202 via supply pipe 210
Sodium cooling agent) driving, the high capacity pump is with about 300 gallon per minute of capacity.First distance D1 and second distance D2 difference should
The risk that sodium after being enough to reduce return, processing is drained into supply pipe 210 from recurrent canal 212.In the example shown, between being somebody's turn to do
Away from can be about 3 meters, about 5 meters or about 7 meters.In another example, the spacing can be about 5.5 meters.It is contemplated that it is other separate away from
From.Consider other factorses when measuring the first distance D1 and second distance D2.For example, it may be desirable to when reactor holds with 100%
(consider thermal expansion of sodium etc.) under the liquid level of sodium of the first distance D1 in hot pond 108 during amount operation.Second distance D2 should
In reactor vessel 202 on the minimum level of acceptable sodium so that main sodium processing system 300 is not by the sodium of container
208 liquid level can still remove caesium (and the heat of bottom line in the case of being pumped under minimum cooling liquid level from sodium cooling agent
Amount).Because the direct cooling of the sodium in reactor vessel 202 is performed by direct heat exchanger 218, so by direct heat exchanger
218 entrance 220 is positioned at the refrigerating function for contributing to preserve direct heat exchanger 218 at the 3rd distance D3.Because the
Under the second distance D2 of supply pipe, second distance D2 is being preserved needed for the cooling in reactor vessel 202 three distance D3
On minimum sodium height.
Below reactor lid 204, one or more direct heat exchangers are also configured with reactor vessel 202
218.Direct heat exchanger 218 includes the entrance 220 for being used for the relatively hot sodium that position is higher in reactor vessel 202.Should
Entrance 220 is configured at the 3rd distance D3 bigger than second distance D2 below the basal plane；Therefore, entrance 220 is in main sodium processing system
Under the height of supply pipe 210.The outlet 222 relatively cold sodium of direct heat exchanger 218 (be used for have been subjected to) is located at than the
At the 5th big three distance D3 distance D5.Direct reactor cooling tube (being illustrated in Fig. 1 as 136) and direct heat exchanger
218 connect and allow the direct cooling of the sodium in reactor vessel 202 as described above for safety or other purposes.
Below reactor lid 204, one or more intermediate heat exchangers are also configured with reactor vessel 202
224.Intermediate heat exchanger 224 includes the entrance 226 for being used for the relatively hot sodium that position is higher in reactor vessel 202.Should
Entrance 226, which configures, to be compared below basal plane at the 4th big distance D4 of the 3rd distance D3；Therefore, entrance 226 is leading to directly heat friendship
Under the height of the entrance 220 of parallel operation 218.Outlet 228 (being used for the relatively cold sodium for having been subjected to intermediate heat exchanger 224) position
At the sixth distance D6 bigger than the 4th distance D4, and in cold drop 230.Intermediate heat pipe (shows as 126 in Fig. 1
Go out) it is connected with being located away from the electricity generation system of reactor vessel 202 (and being illustrated in Fig. 1 as 123).Heat-transfer pipe is anti-
Answer and be connected in heap container 202 with intermediate heat exchanger 224.
With nuclear reaction occurs in core body 216, a large amount of neutrons are launched therefrom.These neutrons, which can activate, to be cycled through
Between heat exchanger 225 and be recycled to the sodium of steam generating system, this is undesirable.Therefore, intermediate heat exchanger 224 is shielded
To prevent this activation.In one example, stainless steel can be used as the outer cover of intermediate heat exchanger 224 for shielding.
However, fully shielding will need thick stainless steel outer wall, will change in long-term its characteristic after reaction.Therefore, carried
The technology gone out is contemplated using boronated steel intermediate heat exchanger 224 and the NEUTRON EMISSION from reactor core body 216 to be shielded.
Boronated steel can use the form for the sheath 232 for partially or completely surrounding intermediate heat exchanger 224.Boronated steel can profit
The stainless steel outer cover of intermediate heat exchanger 224 is soldered to the welding technique for the leafing for preventing sheath 232.Boron is carried in order to limit
Change the overall size of the intermediate heat exchanger 224 of steel sheath 232, sheath 232 can be installed only at a part of intermediate heat exchanger 224
Around.For example, sheath 232 can cover intermediate heat exchanger 224 at least in part with reactor core body 216 to region
(that is, intermediate heat exchanger 224 by exposed to the part for the neutron bombardment launched from core body 216).It can calculate along intermediate heat
These NEUTRON EMISSIONs at the diverse location of the height of exchanger 224, and sheath 232 may extend under reactor lid 204
Position at the predetermined 7th distance D7 of side, to ensure fully to shield.In one example, the 7th distance D7 can be more than and represent
Lead to the 4th distance D4 of the entrance 226 of intermediate heat exchanger 224.
In addition, boronation steel sheath 232 can extend downwardly into the boss portion 234 that Jiang Rechi 208 separates with cold drop 230
Position.NEUTRON EMISSION into cold drop 230 is not easy to influence the part configured wherein of intermediate heat exchanger 224；Therefore, shield
It is not required, but shielding can be included in the case of needing or be desired in a particular application.
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 style, and be not intended to be limited.It must be noted that as used in this manual, 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 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 (11)
- A kind of 1. reactor system, it is characterised in that including：Reactor vessel；Reactor lid, the reactor lid configuration is on the reactor vessel；WithMain sodium processing system supply pipe and main sodium processing system recurrent canal, wherein the main sodium processing system supply pipe and the master Each of sodium processing system recurrent canal all penetrates the reactor lid, and wherein described main sodium processing system supply pipe The length extended below the reactor lid than the main sodium processing system recurrent canal under the reactor lid Fang Yanshen length length.
- 2. reactor system according to claim 1, it is characterised in that also include：The direct heat exchanger in the reactor vessel and below the reactor lid is configured, wherein described direct Heat exchanger includes configuring the entrance and exit below the reactor lid, and wherein described direct heat exchanger Entrance, which is located at below the reactor lid, is more than prolonging below the reactor lid for the main sodium processing system supply pipe At the distance for the length stretched.
- 3. reactor system according to claim 2, it is characterised in that also include：The intermediate heat exchanger in the reactor vessel and below the reactor lid is configured, wherein the centre Heat exchanger includes configuring the entrance and exit below the reactor lid, and wherein described intermediate heat exchanger Entrance be located at below the reactor lid than the direct heat exchanger entrance below the reactor lid away from From place with a distance from big.
- 4. reactor system according to claim 2, it is characterised in that also include penetrate the reactor lid and A pair of direct reactor cooling tubes that opening position in the reactor vessel is connected with the direct heat exchanger.
- 5. reactor system according to claim 3, it is characterised in that also include penetrate the reactor lid and A pair of intermediate heat delivery pipes that opening position in the reactor vessel is connected with the intermediate heat exchanger.
- 6. reactor system according to claim 3, it is characterised in that the outlet of the direct heat exchanger is positioned at described Below reactor lid at the distance bigger than the distance that the entrance of the intermediate heat exchanger is located at below the reactor lid.
- 7. reactor system according to claim 3, it is characterised in that the intermediate heat exchanger includes four intermediate heats Exchanger.
- 8. reactor system according to claim 3, it is characterised in that also include configuration in the reactor vessel Boss portion, wherein at least a portion of the intermediate heat exchanger is configured below the boss portion.
- 9. reactor system according to claim 8, it is characterised in that the intermediate heat exchanger coats at least in part There is boronated steel.
- 10. reactor system according to claim 8, it is characterised in that the diameter of the intermediate heat exchanger is about Half is wrapped by.
- 11. reactor system according to claim 8, it is characterised in that the configuration of only described intermediate heat exchanger is in institute State the part above boss portion and be coated with boronated steel.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US201762477753P | 2017-03-28 | 2017-03-28 | |
| US62/477753 | 2017-03-28 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN207038183U true CN207038183U (en) | 2018-02-23 |
Family
ID=61468220
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201720697359.8U Expired - Fee Related CN207038183U (en) | 2017-03-28 | 2017-06-15 | Reactor system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN207038183U (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110767331A (en) * | 2019-11-05 | 2020-02-07 | 中国科学院合肥物质科学研究院 | Box top cap of piling of small-size liquid metal reactor |
| CN112466480A (en) * | 2020-11-30 | 2021-03-09 | 上海交通大学 | Modularization traveling wave reactor |
-
2017
- 2017-06-15 CN CN201720697359.8U patent/CN207038183U/en not_active Expired - Fee Related
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110767331A (en) * | 2019-11-05 | 2020-02-07 | 中国科学院合肥物质科学研究院 | Box top cap of piling of small-size liquid metal reactor |
| CN112466480A (en) * | 2020-11-30 | 2021-03-09 | 上海交通大学 | Modularization traveling wave reactor |
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Granted publication date: 20180223 |