CN207489489U - Central core monitoring device component - Google Patents
Central core monitoring device component Download PDFInfo
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- CN207489489U CN207489489U CN201720780065.1U CN201720780065U CN207489489U CN 207489489 U CN207489489 U CN 207489489U CN 201720780065 U CN201720780065 U CN 201720780065U CN 207489489 U CN207489489 U CN 207489489U
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- central core
- monitoring device
- device component
- core monitoring
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- 238000012806 monitoring device Methods 0.000 title claims abstract description 35
- 239000000446 fuel Substances 0.000 claims description 29
- 238000012544 monitoring process Methods 0.000 claims description 15
- 238000004154 testing of material Methods 0.000 claims description 8
- 230000000712 assembly Effects 0.000 claims description 5
- 238000000429 assembly Methods 0.000 claims description 5
- 239000000523 sample Substances 0.000 claims description 5
- 238000007789 sealing Methods 0.000 claims description 3
- 239000000306 component Substances 0.000 description 54
- 239000002826 coolant Substances 0.000 description 34
- 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 33
- 229910052708 sodium Inorganic materials 0.000 description 33
- 239000011734 sodium Substances 0.000 description 33
- 239000008358 core component Substances 0.000 description 18
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 12
- 230000004992 fission Effects 0.000 description 9
- 229910052770 Uranium Inorganic materials 0.000 description 8
- 239000007788 liquid Substances 0.000 description 6
- 230000004907 flux Effects 0.000 description 5
- 239000007789 gas Substances 0.000 description 5
- 239000000463 material Substances 0.000 description 5
- 230000007246 mechanism Effects 0.000 description 4
- 230000004888 barrier function Effects 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 238000003780 insertion Methods 0.000 description 3
- 230000037431 insertion Effects 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 230000005540 biological transmission Effects 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000005611 electricity Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 241000208340 Araliaceae Species 0.000 description 1
- 235000005035 Panax pseudoginseng ssp. pseudoginseng Nutrition 0.000 description 1
- 235000003140 Panax quinquefolius Nutrition 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
- 229910052786 argon Inorganic materials 0.000 description 1
- 229910052797 bismuth Inorganic materials 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000004200 deflagration Methods 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 230000029142 excretion Effects 0.000 description 1
- 239000011888 foil Substances 0.000 description 1
- 235000008434 ginseng Nutrition 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000003999 initiator Substances 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 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
- 238000003032 molecular docking Methods 0.000 description 1
- 230000008450 motivation Effects 0.000 description 1
- 238000002139 neutron reflectometry Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- BITYAPCSNKJESK-UHFFFAOYSA-N potassiosodium Chemical compound [Na].[K] BITYAPCSNKJESK-UHFFFAOYSA-N 0.000 description 1
- 230000035755 proliferation Effects 0.000 description 1
- 230000000644 propagated effect Effects 0.000 description 1
- 230000001681 protective effect Effects 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 239000003507 refrigerant Substances 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 230000003068 static effect Effects 0.000 description 1
- 238000012360 testing method 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model provides a kind of central core monitoring device component, including：Exsertile instrument pipe unit, including Instrument assembly；And guide assembly, the guide assembly can be operated selectively with the middle position by the exsertile instrumentation tube cell location in reactor core.
Description
Technical field
The utility model is related to nuclear reaction field more particularly to a kind of central core monitoring device components.
Background technology
Thailand draw energy traveling wave reactor (TWR) fission equipment (its more generally can be described as nuclear fission deflagration wave reactor or
Nuclear burning wave reactor) in, key reaction pile element is to be filled with the reactor vessel of Liquid Sodium cooling agent and reactor core.
TWR fissions equipment is the through type fast reaction heap of subcritical heavily loaded operating fuel for being proliferated and burning by scene.Reactor
Core is immersed in the sodium pond in reactor vessel.It is by depleted uranium/exhaustion uranium (U-238) in the center of core in a kind of design
Stick surround some enriched uranium (U-235) stick.U-235 is used as initiator, starts traveling wave reaction under external force ---
A kind of slow mobile chain reaction of the parallel fission wave advanced through uranium bar.These parallel waves cause in the center of core, so as to slow
It slowly consumes fuel and generates heat in the core.This operational mode is visually expressed as wherein proliferation and and then is burnt sometimes
The reactor that the wave of fissile material will be advanced relative to fuel.However, the TWR of the safe drawing energy fissions, equipment further includes so-called
" standing wave " designs, and exhausts uranium bar with not exhausting uranium bar from reactor core external week wherein near the center of reactor core
It exchanges as the alternative solution that reaction is made radially outward to be propagated through static stick.
Sodium cooling agent is used to radiate from core.Containment surrounds reactor vessel to leak from reactor vessel in contingency
In the case of prevent the loss of sodium cooling agent.Pump make main sodium cooling agent reactor core and the intermediate heat exchanger in the pond it
Between recycle.These heat exchangers have the intermediate sodium cooling agent of on-radiation in the opposite side of heat exchanger.Heated centre
Sodium cooling agent, which is recycled to, generates steam to drive the steam generator of the turbine of generator.
Theoretically, TWR equipment of fissioning does not need to fuel reprocessing, using depleted uranium or natural uranium as their main fuel,
A small amount of enriched uranium is only needed at the start, and nevers need to refuelling again.This core longevity depends on the first dress of uranium
The specification of material and the fuel burn-up rate realized during reactor operation.
Utility model content
In an arrangement, which is related to a kind of central core monitoring device component, has：Exsertile instrumentation tube
Unit, including Instrument assembly；And guide assembly, the guide assembly are selectively operable to exsertile instrument pipe unit
It is located in the middle position in reactor core.In one example, be dimensioned to can be into for exsertile instrument pipe unit
Enter in centrally located instrument sleeve.In another example, Instrument assembly includes neutron detector.In another example,
Instrument assembly includes flow probe.In yet another example, Instrument assembly includes hygrosensor.
In another example of above-mentioned aspect, exsertile instrument pipe unit includes upper detector unit, intermediate detection
Device unit and lower part detector cells.In one example, upper detector unit, intermediate detector unit and lower part detector
Each of unit all includes flow probe, temperature sensing and neutron detector.In another example, middle position is neighbouring
Multiple fuel assemblies.In another example, middle position is adjacent to six fuel assemblies.In yet another example, six fuel stacks
Part is feeding fuel assembly.
In another example of above-mentioned aspect, instrument bush structure is into the testing of materials group with being arranged in reactor core
Part coordinates, which includes multiple samples.In one example, the first end of central core monitoring device is being reacted
Extend above heap head cover；And wherein the first end of central core monitoring device component including centrally located core monitoring device and
Sealing element between second end, second end are opposite with first end.In another example, central core monitoring device includes being located at anti-
The port in heap head cover is answered, which is located in the rotating piston in reactor lid, which can rotate to multiple positions.
In another example, exsertile instrument pipe unit is constructed to be permeable to be retracted into ontology during refueling operation.
Description of the drawings
Below form the application a part attached drawing be for described technology it is illustrative and be not intended to
Any mode limits the range for the technology for requiring patent right, 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 plan view from above of the exemplary reaction pile component in traveling wave reactor.
Fig. 3 is side sectional view of the reaction pile component shown in Fig. 2 along line V-V.
Fig. 4 is the sectional perspective view of the reactor lid head cover of traveling wave reactor.
Fig. 5 is the schematic side plan view of the central core monitoring device component of traveling wave reactor.
Fig. 6 is the part with the central core monitoring device component of Fig. 5 of the part docking for reacting pile component of Fig. 2
Schematic cross sectional side view.
Specific embodiment
Fig. 1 is shown in block diagram form some basic building blocks of traveling wave reactor (TWR) fission equipment 100.In general,
TWR fission equipment 100 includes accommodating the reactor core 102 of multiple fuel assembly (not shown).Core 102 is arranged on holding one
In the pond 104 for determining the Liquid Sodium cooling agent 106 of volume.Pond 104 is referred to as hot pond and with than also accommodating Liquid Sodium cooling agent
The high sodium temperature of 106 surrounding's cold drop 108 (is attributed to the energy generated by the fuel assembly in reactor core 102).Heat
Pond 104 is separated by elbows 110 and cold drop 108.The overhead space 112 of the ullage of sodium cooling agent 106 is filled with such as
The inert protective gas of argon gas.Reactor vessel 114 surrounds reactor core 102, hot pond 104 and cold drop 108, and using instead
Heap head cover 116 is answered to seal.Reactor lid 116 provides a variety of maintenance points led in the inside of reactor vessel 114.
The size of reactor core 102 is selected based on Multiple factors, the characteristic including fuel, desired generated energy, can
100 space of reactor of acquisition etc..TWR fission equipment a variety of examples can as needed or it is expected be used for low-power (about
300MWeAbout 500MWe), middle power (about 500MWeAbout 1000MWe) and high power (about 1000MWeMore than) application in.It can lead to
Crossing the unshowned one or more reflectors of the setting around core 102 and being returned to neutron reflection improves reaction in core 102
The performance of heap 100.It is moved in the core 102 and around it (or " in addition, fissile material and fissible nuclear component can be generated
Change ") to control the nuclear reaction that wherein occurs.
Sodium cooling agent 106 is recycled via main sodium cooling agent pump 118 in container 114.Main coolant pump 118 is from cold drop 108
It aspirates sodium cooling agent 106 and it is ejected into pumping chamber (plenum) below reactor core 102.Cooling agent the last 106
It makes upwardly through core and is heated due to the reaction occurred in reactor core 102.The cooling agent 106 of heating is from warm
Pond 104 enters intermediate heat exchanger (multiple) 120, and leaves intermediate heat exchanger 120 and reenter cold drop 108.It is this
Main Coolant loop 122 thus makes sodium cooling agent 106 be recycled in reactor vessel 114 completely.
Intermediate heat exchanger 120 combines to be physically separate from main sodium pond 104 and 108 (that is, intermediate sodium and main sodium are forever always
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 transmitted 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 (so that the sodium 106 in Main Coolant loop 122 is allowed to flow therebetween
It is dynamic).In one example, four intermediate heat exchangers 120 are distributed in container 114.Alternatively, two or six intermediate heat exchanges
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.Intermediate sodium pump 128 outside reactor vessel 114 makes sodium cooling agent 126 be recycled to electricity generation system 123.Heat is cold from master
But the sodium cooling agent 106 of agent loop 122 is transmitted to the sodium cooling agent of the intercoolant loop 124 in intermediate heat exchanger 120
126.The sodium cooling agent 126 of intercoolant loop 124 passes through multiple pipes 130 in intermediate heat exchanger 120.These pipes 130
The sodium cooling agent 106 and the sodium cooling agent 126 of intercoolant loop 124 for keeping Main Coolant loop 122 separate, simultaneously
Transferring heat energy therebetween.
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 the Main Coolant loop 122 and direct heat exchanger cooling agent NaK of direct reactor coolant loop 138
136 separate, while transferring heat energy therebetween.
Other assisted reaction pile elements (be located 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, check-valves, shut-off valve, flange, excretion to those skilled in the art
Slot etc..Across reactor lid 116 other through hole (for example, port, inertia covering gas for main refrigerant pump 118
Body and inspection port, sodium processing port and revenge gas ports 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 present disclosure describes the configurations for the performance for improving reactor 100 shown in FIG. 1.Specifically, for supervising
Example, configuration and the arrangement for controlling the central core monitoring device component of the performance of reactor 100 are shown and join below
Figure below is examined to be more fully described.
Fig. 2-6 shows multiple views of exemplary centric core monitoring device (CCMD) component 200.It is not shown in the various figures
Each component described below.In figure for the sake of clarity, multiple reaction pile elements are omitted.Other embodiments can include or
More or few components.
Fig. 2 is the plan view from above of the exemplary reaction pile component in traveling wave reactor, and Fig. 3 is reaction shown in Fig. 2
Pile component along line V-V side sectional view.Reactor core 226 is shown in figs 2 and 3.In this embodiment, it is central
Core component 214 is located substantially at the geometric center in the section of reactor core 226.Central core component 214 is preferably not
The component of refuelling.In addition, central core component 214 is configured to for the insertion of instrumentation tube (not shown), wherein instrumentation tube packet
Include one or more detectors or sensor.Hereinafter the instrumentation tube is discussed in more detail with particular reference to Figures 5 and 6.
Multiple active fuel components 228 are set close to central core component 214.As shown in the figure, adjacent central core component
Each in 214 six fuel assemblies 228 is feeding fuel assembly.Other configurations of reactor core 226 can have
The fuel assembly 228 of more or less adjacent central core component 214.In addition feeding fuel assembly is from central core component
214 extend radially outwardly.Fuel assembly 228 in the multiple encirclement reactor of reflector assemblies 230 cores 226, and shield assembly
231 surround reflector assembly 230.The different sums of component are possible, size and structure depending on reactor core 226
Type.
Fig. 4 shows the sectional view of the reactor lid 220 of bearing CCMD components 200.Reactor lid 220 is via attachment
CCMD nozzles 205 to the head cover of reactor lid 220 support CCMD components 200.More specifically, CCMD nozzles 205 are attached to
Small rotating piston 224 and near multiple control rod drive mechanism ports 242.CCMD components 200 have been not shown in Fig. 4,
But it will be mounted on and be located at CCMD ports 202.
CCMD components 200 (being not shown in Fig. 4) extend through above head cover from the position via CCMD ports 202
Reactor lid 220, and extend downwardly and (be shown in fig. 1-3) near the head cover of reactor core.CCMD ontologies 204
It is supported by CCMD ports 202 and is along its length extended to terminate just above reactor core 226.CCMD components
200 are adjusted relative to the located lateral of reactor core 226 via the rotation of big rotating piston 222 and/or small rotating piston 224.
Central core monitoring device port 202 is located on reactor lid 220, and in standby and control rod drive mechanism array
Central core monitoring device ontology 204 is centrally located right over core component (Fig. 2 during the usual operation of reactor
With 3).
Fig. 5 is the side sectional view of exemplary CCMD components 200.In general, CCMD components 200 are by the way that Instrument assembly is selected
Drop to selecting property the middle position of reactor core body 226 to provide work(of the monitoring in the reactor core performance of various times
Energy.By the way that Instrument assembly is centrally located reactor core body position, from 360 degree of acquisition performance numbers around Instrument assembly
According to.The part extended into reactor core of Instrument assembly can be pulled out, such as during refueling operation in a variety of times
With may damage apparatus components operation during.CCMD components 200 are mainly used for obtaining in the center of reactor core 226
Axial neutron flux data, although as described below, CCMD components 200 can be configured to obtain other data.
CCMD components 200 include sealing and rising, fall a variety of components with guide instrument pipe 212.In general,
CCMD components 200 include central core monitoring device port 202, central core monitoring device ontology 204 and instrumentation tube 212.
CCMD ontologies 204 include being configured to rise or fall instrumentation tube 212 and seal inside to prevent the gas above reactor lid
The various components of any effusion of body or liquid.Preferably, in order to carry out axial flux monitoring in the whole length of fuel region,
Instrumentation tube 212 is inserted into the bottom of fuel region, and in some embodiments, is inserted into the bottom part down of fuel region.
Instrumentation tube 212 is the extended mesotube that a variety of apparatus is allowed to be inserted into core.In addition, instrumentation tube 212 can
The monitoring demand of a range during holding equipment initial start and/or operation.EXEMPLARY MONITOR demand includes：Neutron is supervised
Control, monitoring temperature and traffic monitoring.For example, monitoring can be used for along fuel rod by the Instrument assembly that CCMD components 200 provide
The axial flux profile of length.Other monitoring instruments are used together with CCMD components 200.
In operational mode, instrument dry-well 212 extends into instrument sleeve 208 from CCMD ontologies 204 and accommodates instrument
Component 215.Instrument dry-well 212 extends to instrument and axial barrier 217.In order into and out instrument, drive component (following ginseng
Examine Fig. 5 discussion) it rises and falls instrument dry-well 212.One end of instrument dry-well 212, which can be removed, can include axial barrier 217.Axis
Shielding is provided them to extend detector or instrument when detector or instrument are pulled out under high reactor capability to barrier 217
The service life of device.In some embodiments, Instrument assembly 215 includes single monitoring detector, such as axial flux detector.Another
In some embodiments, Instrument assembly 215 includes the monitoring detector for being located at the single type of three different locations.More yet another
In embodiment, Instrument assembly 215 includes a plurality of types of detectors more in single position or in multiple positions.
Fig. 5 also shows that the illustrative configuration of Instrument assembly 215.As shown in the figure, Instrument assembly 215 is included relative to reactor
Fuel is located at the detector of three positions：Upper detector unit 232, intermediate detector unit 234 and lower part detector cells
236.Upper detector unit 232, intermediate detector unit 234 and lower part detector cells 236 are along central core component 214
Length is preferably equally spaced apart to provide reliable monitoring.Other arrangements are possible.
Drive component 260 selectively rises and falls removable instrument dry-well 212.Drive component 260 passes through rise
Or it falls the cooperations of the various components of the hawser 261 that is attached to removable instrument dry-well 212 and removable instrument is controlled to do
The height of well 212.Fig. 5 shows to include driving motor 262, gear reduction unit 264, hawser reel 266 and detector/instrument electricity
The component of one embodiment of the drive component 260 of cable/signal wire 268.Transmission mechanism 270 passes through CCMD ontologies 204 and by passing
Motivation structure bearing supports.External screw thread on transmission mechanism 270 be attached to the ball-screw 272 of telescopic sleeve 208 dock with
It falls and rises instrument sleeve 208.Metal bellows 206 is arranged in CCMD ontologies 204, so that CCMD ontologies 204 are close
238 lower section of sodium liquid level is enclosed in prevent sodium from being sprayed above reactor lid via CCMD components 200.
With reference to Fig. 6, central core component 214 includes guiding funnel 216, in top droop thus to facilitate instrumentation tube
212 protrude out into instrument sleeve 208 with it from CCMD ontologies 204.Guiding tube 210 guiding in CCMD is provided so that
Instrumentation tube 212 is felt relieved above core component 214.In an example shown, CCMD components 200 do not contact central core component
214 manipulation tube socket, but there are ample clearance so that big rotating piston 222 and small rotating piston 224 can be directed to fuel manipulation
The promotion or removal operated without main CCMD ontologies 204.
In the shown embodiment, central core component 214 further includes testing of materials component 218.Testing of materials component 218 wraps
Include the sample and/or sealed sample for monitoring reactor behavior at any time.For example, reactor core member radiative material test group
Component inside part 218, wherein the component can be stainless steel, foil etc..As shown in the figure, testing of materials component 218 limit with
The hole or channel that instrument sleeve 208 matches, Instrumental sleeve 208 enable instrumentation tube 212 by wherein.In addition, as schemed
It is shown, the hole limited by testing of materials component 218 or channel centering.In further embodiments, it is limited by testing of materials component 218
Fixed entirety eccentric can position.
During reactor is usually run, instrumentation tube is lowered in instrument sleeve 208.Preferably, instrument sleeve 208 extends
The overall length of central core component 214.The promotion monitoring instrument of instrument sleeve 208 and potentially Other Instruments are to them in core
The insertion and guiding of interior fully inserted position.Thus, it is possible to obtain the axial flux wheel across entire reactor core 226
It is wide.One example of partial insertion position is shown in figure 6.Add since the instrument sleeve 208 of whole length will limit to come from
Fuel assembly exits flowing, so central core component 214 is not the core component of refuelling.During refueling operation,
The instrument sleeve 208 of instrumentation tube 212 from central core component 214 is pulled out and big rotating piston 222 and small rotating piston 224 can revolve
Turn so that CCMD components 200 are moved to the position being misaligned with central core component 214.It is big to rotate during refueling operation
Plug 222 and small rotating piston 224 move their own operating position, and instrumentation tube 212 reinserts instrument sleeve 208
In.
It should be understood that although providing the above disclosure with TWR fission device-dependents, structure described herein is fitted
For in other fast reaction heaps.For example, CCMD components 200 can be used for sodium cooling formula fast reaction heap, lead or lead-bismuth cooled
Fast reaction heap and/or using supporting in other reactors of cooling agent for composing soon.
It should also be understood that the present disclosure is not limited to specific structure disclosed herein, processing step or material, but extend to related neck
Domain skilled artisan will realize that their equivalent.It should also be understood that term used herein is merely for the sake of description
The purpose of specific example, and be not intended to be limited.It must be noted that as used in the present specification, singulative
One feeding, a feeding and the feeding include the reference of plural number, 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 perhaps
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 disclosure, various changes and modifications can be made, well
In the range contemplated by the disclosure.Those skilled in the art, which can be made, will arbitrarily expect and covered in the disclosure
Spirit in many other changes.
Claims (14)
- A kind of 1. central core monitoring device component for monitoring reactor core, which is characterized in that the central core monitoring device Component includes：Exsertile instrument pipe unit, the instrument pipe unit include Instrument assembly, which is used to monitor the reactor core At least one of internal neutron, temperature and flow；WithGuiding tube, the guiding tube can selectively operate with by the exsertile instrumentation tube cell location in the reactor core Middle position in body.
- 2. central core monitoring device component according to claim 1, which is characterized in that the exsertile instrumentation tube list The size of member is set to enter in the instrument sleeve of the middle position.
- 3. central core monitoring device component according to claim 1, which is characterized in that the Instrument assembly includes neutron Detector.
- 4. central core monitoring device component according to claim 3, which is characterized in that the Instrument assembly includes flow Detector.
- 5. central core monitoring device component according to claim 4, which is characterized in that the Instrument assembly includes temperature Detector.
- 6. central core monitoring device component according to claim 1, which is characterized in that the exsertile instrumentation tube list Member includes upper detector unit, intermediate detector unit and lower part detector cells.
- 7. central core monitoring device component according to claim 6, which is characterized in that the upper detector unit, Each of the intermediate detector unit and the lower part detector cells all include flow probe, hygrosensor and Neutron detector.
- 8. central core monitoring device component according to claim 1, which is characterized in that the middle position is adjacent to multiple Fuel assembly.
- 9. central core monitoring device component according to claim 1, which is characterized in that the middle position is adjacent to six Fuel assembly.
- 10. central core monitoring device component according to claim 9, which is characterized in that six fuel assemblies are Feed fuel assembly.
- 11. central core monitoring device component according to claim 1, which is characterized in that the instrument bush structure into Coordinate with the testing of materials component being arranged in the reactor core, the testing of materials component includes multiple samples.
- 12. central core monitoring device component according to claim 1, which is characterized in that central core monitoring device First end extends above reactor lid；AndWherein described central core monitoring device component includes being arranged on first end and the of the central core monitoring device Sealing element between two ends, the second end are opposite with the first end.
- 13. central core monitoring device component according to claim 12, which is characterized in that the central core monitoring dress The port including being arranged in reactor lid is put, the port is located in the rotating piston in the reactor lid, the rotation Rotoplug can be rotated to multiple positions.
- 14. central core monitoring device component according to claim 1, which is characterized in that the exsertile instrumentation tube Unit is constructed to be permeable to be retracted into ontology during refueling operation.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US201762516987P | 2017-06-08 | 2017-06-08 | |
| US62/516987 | 2017-06-08 |
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| Publication Number | Publication Date |
|---|---|
| CN207489489U true CN207489489U (en) | 2018-06-12 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201720780065.1U Expired - Fee Related CN207489489U (en) | 2017-06-08 | 2017-06-30 | Central core monitoring device component |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110211710A (en) * | 2019-06-12 | 2019-09-06 | 中国核动力研究设计院 | A kind of more illuminated target material irradiations test core structure and arrangement and operation method |
| CN112366013A (en) * | 2020-11-10 | 2021-02-12 | 中国核动力研究设计院 | Nuclear test method suitable for heat pipe reactor |
| CN113883083A (en) * | 2021-10-25 | 2022-01-04 | 中国原子能科学研究院 | A main pump and reactor for reactor |
-
2017
- 2017-06-30 CN CN201720780065.1U patent/CN207489489U/en not_active Expired - Fee Related
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110211710A (en) * | 2019-06-12 | 2019-09-06 | 中国核动力研究设计院 | A kind of more illuminated target material irradiations test core structure and arrangement and operation method |
| CN110211710B (en) * | 2019-06-12 | 2022-03-25 | 中国核动力研究设计院 | Multi-irradiation target material irradiation inspection reactor core structure and arrangement and operation method |
| CN112366013A (en) * | 2020-11-10 | 2021-02-12 | 中国核动力研究设计院 | Nuclear test method suitable for heat pipe reactor |
| CN112366013B (en) * | 2020-11-10 | 2022-04-15 | 中国核动力研究设计院 | Nuclear test method suitable for heat pipe reactor |
| CN113883083A (en) * | 2021-10-25 | 2022-01-04 | 中国原子能科学研究院 | A main pump and reactor for reactor |
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