CN105989902A - Sample design method used for research of nuclear fusion device castellation part structure - Google Patents
Sample design method used for research of nuclear fusion device castellation part structure Download PDFInfo
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- CN105989902A CN105989902A CN201510982035.4A CN201510982035A CN105989902A CN 105989902 A CN105989902 A CN 105989902A CN 201510982035 A CN201510982035 A CN 201510982035A CN 105989902 A CN105989902 A CN 105989902A
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- castellations
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
- G21B1/13—First wall; Blanket; Divertor
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/10—Nuclear fusion reactors
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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Sampling And Sample Adjustment (AREA)
Abstract
The invention discloses a sample design method used for the research of a nuclear fusion device castellation part structure. A slot of certain depth and width is arranged in the bottom part of the side surface of a first wall material component, and a connecting strip matched with the slot is inserted in the slot. Different first wall material components are rapidly assembled together to form the plasma facing castellation part structure of a fusion device. The width and the depth of the part gaps can be controlled by adjusting the position of the slots and the width of the strips. Different gap profiles and surface shapes can be acquired by performing appropriate cutting on the side surfaces, the edges and the corners and the top parts of the components. The assembled component samples are arranged in a sample base with graded slots, the surface is level, and great contact with the bottom part of the sample base is formed through extrusion of the screws arranged at the side surfaces.
Description
Technical field
The present invention relates to nuclear fusion device field, a kind of for nuclear fusion device castellations structural research
Sample design method.
Background technology
In order to have reliable structural stability and hot removal ability under high heat load effect, and electromagnetic force is pressed down
System, in engineering, PFC is usually designed to little tile fragment structure, the most so-called castellation (Castellation structure).
Fuel retention problems in fusion facility is always by extensive concern, and this is mainly due to ITER and following fusion dress
Putting will be with active tritium as raw material.Considering from a safety viewpoint, the tritium hold-up allowed in ITER is 700 grams.Higher
Fuel be detained will seriously limit the number of times of safe-discharge, for this point, only can remove the tritium in ITER device,
The D-T fusion reaction that ITER plan is carried out could persistently be carried out.The effectively monitoring that hydrogen isotope is detained and assessment, the most right
The effectively control being detained at tile fragment gap is one of Tough questions faced in ITER design phase and Physical Experiment in future.For
Basic feature that this problem is detained firstly the need of the impurity deposition understood in castellation gap and its fuel of causing and
Mechanism.Additionally, the little tile fragment part split by gap in this castellation just part to the magnetic line of force is formed so-called prominent
Go out corner angle, and manufacture and inevitable slight error in installation process, make little tile fragment surface not flush completely, may aggravation
The problem of prominent corner angle.Easily form focus (hot spots) herein, cause hot-spot even to melt.By to little watt
Block part corner angle or surface carry out suitable cutting, it is possible to reduce this overheated, protect tile fragment corner angle, extend castellation portion
The life-span of part.These optimize design needs to carry out experimental verification in fusion facility.
The postmortem analysis of the component materials in fusion facility needs to carry out in Laboratory Instruments, and these instruments are to analyzing sample
The size shape of product has strict requirements, it is impossible to detect the impurity in gap and fuel droplets, and at fusion facility
Experiment carries out cutting to monoblock tile fragment after terminating can produce dust pollution, and local temperature during cutting raises also can make sample oxygen
Changing, these all can have a strong impact on the accuracy of instrument analysis results afterwards.
Summary of the invention it is an object of the invention to provide a kind of sample for nuclear fusion device castellations structural research
Method for designing, to solve the problem that in prior art nuclear fusion device, castellation exists.
In order to achieve the above object, the technical solution adopted in the present invention is:
A kind of sample design method for nuclear fusion device castellations structural research, it is characterised in that: at the first wall material
Material part side bottom level has the slit of certain depth and width, inserts the connection slice matched, by difference first
Wall material part quickly fits together and forms fusion facility in the face of the castellations structure of plasma；By adjusting slit
Position, connection slice width control system castellations structure gap width, the degree of depth, by plasma facing material part side, rib
Angle and top suitably cut, it is thus achieved that different gap sections and surface configuration；The castellations structure sample that will assemble
Product are loaded in the specimen holder with dovetail groove, and surface flushes, and are extruded by side screw, formed with specimen holder bottom well connect
Touch.
A kind of described sample design method for nuclear fusion device castellations structural research, it is characterised in that:
Described plasma facing material part, connection slice material are in the face of plasma material or base layer structure for tokamak device
Material, can be graphite or carbon-fiber reinforced carbon or tungsten or molybdenum or beryllium or rustless steel or copper.
A kind of described sample design method for nuclear fusion device castellations structural research, it is characterised in that:
Plasma facing material part side slot and the cross section basic configuration connecting slice are rectangle, and end face can be plane or cambered surface, connect
Slice can be single strip, it is possible to be combined together to form cross or rich word shape for multiple perpendicular or parallel bar, connects multiple the
One wall material part forms an overall castellations structure；Change slot position and slice width, make castellations tie
Gap in structure has different depth and width.
A kind of described sample design method for nuclear fusion device castellations structural research, it is characterised in that:
The side of plasma facing material part can vertically can also tilt, and forms rectangle, trapezoidal cross section, gap；Plasma facing material part
Corner angle and surface can be plane, inclined-plane, circular arc, it is also possible to for polygon, form the city with different surfaces shape facility
Fort shape modular construction.
A kind of described sample design method for nuclear fusion device castellations structural research, it is characterised in that:
Cutting peripheral plasma facing material part lateral surface, making the castellations structural section after assembling is trapezoid, with sample
Dovetail groove in product seat coordinates, and the lateral layout at specimen holder dovetail groove has screw hole, withstands trapezoidal castle by screwing screw
Shape modular construction sample lateral surface, under the cooperation of an other dovetail groove side, produces downward pressure, makes castellations tie
Bottom structure sample and dovetail groove, there is good thermoelectricity contact performance.
The invention provides a kind of sample design method for nuclear fusion device castellations structural research, it is possible to will
Different plasma facing material parts quickly fit together and form fusion facility in the face of the castellations structure of plasma；Permissible
Member slots width, the degree of depth is controlled flexibly, it is thus achieved that different gap sections and surface configuration according to requirement of experiment.Assemble part
Sample can be loaded in the specimen holder with dovetail groove, and surface flushes, good with contacting bottom specimen holder.It is installed in specimen holder
Castellations sample can with other normal in the face of plasma tile fragment together be fixed on tokamak device diverse location, real
The small sample meeting Instrumental Analysis geomery requirement afterwards can be conveniently disassembled into, it is thus achieved that different castellation tops after testing end
The impurity deposition of portion, side, gap and bottom and fuel are detained feature；This kind of structure can also coordinate tokamak in a device
Infrared cameras on device etc. diagnose, it is possible to obtain the Characteristics of The Distribution of Temperature of different castellation, assessment different castellated knot
The engineering design effect of structure.
The invention have the advantage that it can be avoided that the sample contamination after testing, sample being reprocessed and bring, by soon
Speed assembly or disassembly specimen part, can obtain the small sample meeting Instrumental Analysis geomery requirement afterwards.Can control flexibly
Gap width, the degree of depth, cross section and surface configuration in castellation, it is thus achieved that different castellation tops, side, gap and
The impurity deposition of bottom and fuel are detained feature；This kind of structure can also coordinate the infrared phase on tokamak device in a device
Machines etc. diagnose, it is possible to obtain the Characteristics of The Distribution of Temperature of different castellation, the engineering design effect of the different castellation of assessment
Really.
Accompanying drawing explanation
Fig. 1 is that in the present invention, plasma facing material part assembles schematic diagram with being connected slice.
Fig. 2 is that in the present invention, castellations structure assembles schematic diagram with specimen holder.
Detailed description of the invention
As shown in Figure 1 and Figure 2, a kind of sample design method for nuclear fusion device castellations structural research,
One wall material part 1-6 side bottom level has the slit of certain depth and width, inserts the connection slice 7 matched,
Different plasma facing material part 1-6 are quickly fitted together and forms fusion facility in the face of the castellations structure of plasma
8；By adjusting slot position, connecting slice 7 width control system castellations structure 8 gap width, the degree of depth, by the first wall
Material parts 1-6 side, corner angle and top suitably cut, it is thus achieved that different gap sections and surface configuration；To assemble
Castellations structure sample be loaded in the specimen holder with dovetail groove, surface flushes, and is extruded by side screw, formed with
Good contact bottom specimen holder 9.
Plasma facing material part 1-6, connection slice material are in the face of plasma material or base for tokamak device
Rotating fields material, can be graphite or carbon-fiber reinforced carbon or tungsten or molybdenum or beryllium or rustless steel or copper.
Plasma facing material part 1-6 side slot and the cross section basic configuration connecting slice are rectangle, and end face can be plane
Or cambered surface, connecting slice can be single strip, it is possible to be combined together to form cross or rich word shape for multiple perpendicular or parallel bar,
Connect multiple plasma facing material part 1-6 and form an overall castellations structure 8；Change slot position and slice width,
The gap in castellations structure 8 is made to have different depth and width.
The side of plasma facing material part 1-6 can vertically can also tilt, and forms rectangle, trapezoidal cross section, gap；The
The corner angle of one wall material part and surface can be plane, inclined-plane, circular arc, it is also possible to for polygon, formed and have different surfaces
The castellations structure 8 of shape facility.
Peripheral plasma facing material part 1-6 lateral surface is cut, makes castellations structure 8 cross section after assembling be
Trapezoid, coordinates with the dovetail groove in specimen holder 9, and the lateral layout at specimen holder 9 dovetail groove has screw hole, passes through screwing screw
10,11 withstand trapezoidal castellations structure 8 sample lateral surface, under the cooperation of an other dovetail groove side, produce downwards
Pressure, makes have good thermoelectricity contact performance bottom castellations structure sample and dovetail groove.
In the present invention, for nuclear fusion device in the face of the fast demountable sample design of plasma castellation research
Method, the side bottom at plasma facing material part 1-6 has the slit of certain depth and width, inserts the connection matched
Different plasma facing material parts are quickly fitted together and form fusion facility in the face of the castellations of plasma by slice 7
Structure 8；Member slots width, the degree of depth can be controlled, by part side, rib by adjusting slot position, slice width etc.
Angle and top suitably cut, it is possible to obtain different gap sections and surface configuration.The castellations knot that will assemble
Structure sample is loaded in the specimen holder 9 with dovetail groove, and surface flushes, and is extruded by side screwing screw 10 and 11, is formed and sample
The good contact in product seat bottom portion, the tile fragment 12 after assembling completely has the overall dimensions same with standard tile fragment, and aspect fusion is real
Installation in experiment device.
The present invention includes castellations structure 1-6 with slit, is used for assembling and collect gap bottom deposit
The connection slice 7 of particle, has the specimen holder 9 of screw locking structure.Need to design the first of different structure according to experiment
Wall material part 1-6, and the connection slice 7 matched, after assembling, overall dimensions coordinates with specimen holder 9, it is ensured that surface
Flushing, bottom contact is good.
Plasma facing material part 1-6 and connection slice 7, specimen holder 9, it can be graphite, carbon fibre that material installs requirement of experiment
Dimension strengthens carbon (CFC), tungsten, molybdenum, beryllium, rustless steel, copper etc. for tokamak device in the face of plasma material or base layer structure
Material and combinations thereof.
Plasma facing material part 1-6 side slot and the cross section basic configuration connecting slice are rectangle, and end face can be plane
Or cambered surface, connecting slice 7 can be single strip, it is possible to be combined together to form " ten " word or " rich " word for multiple perpendicular or parallel bar
Etc. shape, connect multiple part and form overall castellation parts.Change slot position and slice width, make castellated
Gap in structure member has different depth and width.
The side of plasma facing material part 1-6 can vertically can also tilt, and forms rectangle, the cross section, gap such as trapezoidal；The
The corner angle of one wall material part 1-6 and surface can be plane, inclined-plane, circular arc, it is also possible to for polygon, formed and have different table
The castellation of face shape facility.
Plasma facing material part 1-6 surrounding lateral surface can cut, and makes the castellation section after assembling
For trapezoid, coordinating with the dovetail groove in specimen holder 9, the lateral layout at pedestal dovetail groove has screw hole, passes through screwing screw
10 and 11 withstand trapezoidal instance element lateral surface, under the cooperation of an other dovetail groove side, produce downward pressure, make castle
Bottom shape structure sample and dovetail groove, there is good thermoelectricity contact performance.
Claims (5)
1. the sample design method for nuclear fusion device castellations structural research, it is characterised in that: at the first wall
Material parts side bottom level has a slit of certain depth and width, inserts the connection slice matched, by difference the
One wall material part quickly fits together and forms fusion facility in the face of the castellations structure of plasma；Narrow by adjusting
Groove location, connect slice width control system castellations structure gap width, the degree of depth, by plasma facing material part side,
Corner angle and top suitably cut, it is thus achieved that different gap sections and surface configuration；The castellations structure that will assemble
Sample is loaded in the specimen holder with dovetail groove, and surface flushes, and is extruded by side screw, formed with specimen holder bottom good
Contact.
A kind of sample design method for nuclear fusion device castellations structural research the most according to claim 1,
It is characterized in that: described plasma facing material part, connection slice material are in the face of plasma material for tokamak device
Material or base layer structure material, can be graphite or carbon-fiber reinforced carbon or tungsten or molybdenum or beryllium or rustless steel or copper.
A kind of sample design method for nuclear fusion device castellations structural research the most according to claim 1,
It is characterized in that: plasma facing material part side slot and the cross section basic configuration connecting slice are rectangle, and end face can be plane
Or cambered surface, connecting slice can be single strip, it is possible to be combined together to form cross or rich word shape for multiple perpendicular or parallel bar,
Connect multiple plasma facing material part and form an overall castellations structure；Change slot position and slice width, make city
Gap in the shape modular construction of fort has different depth and width.
A kind of sample design method for nuclear fusion device castellations structural research the most according to claim 1,
It is characterized in that: the side of plasma facing material part can vertically can also tilt, form rectangle, trapezoidal cross section, gap；The
The corner angle of one wall material part and surface can be plane, inclined-plane, circular arc, it is also possible to for polygon, formed and have different surfaces
The castellations structure of shape facility.
A kind of sample design method for nuclear fusion device castellations structural research the most according to claim 1,
It is characterized in that: peripheral plasma facing material part lateral surface is cut, make the castellations structural section after assembling be
Trapezoid, coordinates with the dovetail groove in specimen holder, and the lateral layout at specimen holder dovetail groove has screw hole, by screwing screw top
Live trapezoidal castellations structure sample lateral surface, under the cooperation of an other dovetail groove side, produce downward pressure, make city
Bottom fort shape modular construction sample and dovetail groove, there is good thermoelectricity contact performance.
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| CN201510982035.4A CN105989902B (en) | 2015-12-23 | 2015-12-23 | A kind of sample design method for nuclear fusion device castellations structural research |
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| CN105989902B CN105989902B (en) | 2018-11-13 |
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Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH1123755A (en) * | 1997-07-04 | 1999-01-29 | Toshiba Corp | First wall of nuclear fusion device |
| RU2179340C2 (en) * | 2000-05-06 | 2002-02-10 | Государственное унитарное предприятие "Научно-исследовательский и конструкторский институт энерготехники" | First wall of fusion reactor |
| CN101147207A (en) * | 2005-03-22 | 2008-03-19 | 普兰西欧洲股份公司 | First wall components for a fusion reactor |
| CN101567225A (en) * | 2009-05-26 | 2009-10-28 | 中国科学院等离子体物理研究所 | first wall part with wolfram coat having grid structure |
| CN101845578A (en) * | 2010-05-15 | 2010-09-29 | 徐州工程学院 | First wall part made of doped tungsten-based composite material and preparation method thereof |
| CN102520125A (en) * | 2011-12-17 | 2012-06-27 | 中国科学院等离子体物理研究所 | Plasma facing experimental part with reference corner structure |
| CN102564831A (en) * | 2011-12-07 | 2012-07-11 | 中国科学院等离子体物理研究所 | Method for clamping embedded sample detachable from first wall part of nuclear fusion experimental device for analysis |
-
2015
- 2015-12-23 CN CN201510982035.4A patent/CN105989902B/en not_active Expired - Fee Related
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH1123755A (en) * | 1997-07-04 | 1999-01-29 | Toshiba Corp | First wall of nuclear fusion device |
| RU2179340C2 (en) * | 2000-05-06 | 2002-02-10 | Государственное унитарное предприятие "Научно-исследовательский и конструкторский институт энерготехники" | First wall of fusion reactor |
| CN101147207A (en) * | 2005-03-22 | 2008-03-19 | 普兰西欧洲股份公司 | First wall components for a fusion reactor |
| CN101567225A (en) * | 2009-05-26 | 2009-10-28 | 中国科学院等离子体物理研究所 | first wall part with wolfram coat having grid structure |
| CN101845578A (en) * | 2010-05-15 | 2010-09-29 | 徐州工程学院 | First wall part made of doped tungsten-based composite material and preparation method thereof |
| CN102564831A (en) * | 2011-12-07 | 2012-07-11 | 中国科学院等离子体物理研究所 | Method for clamping embedded sample detachable from first wall part of nuclear fusion experimental device for analysis |
| CN102520125A (en) * | 2011-12-17 | 2012-06-27 | 中国科学院等离子体物理研究所 | Plasma facing experimental part with reference corner structure |
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