CN102610285A - Structure utilizing metal tungsten as first wall material of magnetic confinement reactor - Google Patents
Structure utilizing metal tungsten as first wall material of magnetic confinement reactor Download PDFInfo
- Publication number
- CN102610285A CN102610285A CN2012100696748A CN201210069674A CN102610285A CN 102610285 A CN102610285 A CN 102610285A CN 2012100696748 A CN2012100696748 A CN 2012100696748A CN 201210069674 A CN201210069674 A CN 201210069674A CN 102610285 A CN102610285 A CN 102610285A
- Authority
- CN
- China
- Prior art keywords
- tungsten
- stainless steel
- wall
- magnetic confinement
- wall material
- 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
Images
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
- Y02E30/10—Nuclear fusion reactors
Landscapes
- Powder Metallurgy (AREA)
Abstract
The invention discloses a structure utilizing metal tungsten as a first wall material of a magnetic confinement reactor. Metal tungsten is adopted as the first wall material; a high-heat loading region is formed by heat isostatic pressing welding of the first wall material, an intermediate cooling heat sink material and a rear support material in a sandwich structure; an intermediate adaptation layer is respectively arranged between the metal tungsten and the intermediate cooling heat sink material and between the intermediate cooling heat sink material and the rear support material; cooling channels are distributed on the intermediate cooling heat sink material and the rear support material; a low-heat loading region is formed by heat isostatic pressing welding of the first wall material and the rear support material; an intermediate adaptation layer is arranged between the first wall material and the rear support material; cooling channels are distributed on the rear support material; and the intermediate cooling heat sink material is chromium-zirconium-copper, and the rear support material is martensite/ferritic stainless steel. According to the invention, under the condition that fuel recycle approaches to zero detention, the magnetic confinement reactor meets the requirement of long-time stable operation with low material corrosion and low fuel detention.
Description
Technical field
The present invention relates to fusion reactor, relate in particular to a kind of structure of utilizing tungsten as the first wall material of magnetic confinement reactor.
Background technology
Modern magnetic confinement fusion experimental provision mostly adopts graphite material as facing plasma first wall material.Present stage graphite material pollute because of its good heat shock resistance, article on plasma body are low and a large amount of experimental data be the employing of most of country.But under following reactor high parameter plasma service condition, use graphite that its unsurmountable weakness is arranged: because chemical sputtering can make the annual rate of corrosion of graphite greater than 10 centimetres, serviceable life, the impurity level of reduction and plasma core raise; Neutron irradiation causes the hot physics of graphite and the quick decay of mechanical property (particularly thermal conductance value reduction by a relatively large margin); Fuel deposits economy and safe operation problem of the device that high tritium hold-up is caused in the carbon-coating or the like again.
Though present international thermonuclear fusion experimental reactor (ITER) first wall material adopts beryllium-tungsten-graphite amalgam to adapt to the various operating modes in different thermal loads district; But because fusionplasma is to the high rate of corrosion of low Z material (like beryllium and graphite); The ITER device can only the short time pulsing operation, not competent long-time continuous operation.At present under ITER D-T operating fuel condition, rate of corrosion every year of tungsten is less than 0.1 millimeter.The possible selected material of following magnetic confinement fusion heap has only the tungsten material can be competent at operation continuously under the reactor operating mode; Annual rate of corrosion less than 1 millimeter can be provided; And under greater than 350 degree wall temperature conditions, realize condition, thereby guarantee not change in 10 years the possibility of first wall material near the zero fuel retention rate.
Following reactor need will up to the thermal load of 10MW/m2 from the divertor parts with heat energy fast walking, using high heat conductance, high performance white horse with a black mane zirconium copper is best choice as cooling heat sink, it can play move fast can function.Simultaneously because high flux neutron irradiation in the reactor, martensite/ferritic steel of selecting low activation as structured material to become the common recognition of international fusion circle.
Summary of the invention
The present invention seeks in order to remedy the defective of prior art, provide a kind of utilize purity greater than 99.5%, heavy wall is greater than 20 millimeters the tungsten structure as the first wall material of magnetic confinement reactor.
The present invention realizes through following technical scheme:
A kind of structure of utilizing tungsten as the first wall material of magnetic confinement reactor; The vacuum chamber of magnetic confinement reactor is divided into low load region and high heat load district by institute's affected by hot loading; Low load region comprises high field region and low place; The high heat load district comprises the divertor district, it is characterized in that: all internal vacuum chamber first wall materials of magnetic confinement reactor all are purity greater than 99.5%, heavy wall is greater than 20 millimeters tungsten, and whole first wall structure can stable operation under 350 degree conditions; In the high heat load district; Adopt first wall material metal tungsten and middle cooling heat sink material and back propping material to be welded by the sandwich structure high temperature insostatic pressing (HIP); Middle cooling heat sink material is a thickness greater than 50 millimeters chromium zirconium copper; Back propping material is a thickness greater than low activation martensite/ferritic stainless steel of 300 millimeters, and middle cooling heat sink material, back propping material all are distributed with the cooling duct, so that remove fast from the thermal load of plasma; The middle adaptation layer that 0.5 millimeter is arranged between tungsten and chromium zirconium copper, its starting material constitute the tungsten powder alloyed powder of 10-20% weight and the chrome zirconium copper alloy powder of 80-90% weight; Between chromium zirconium copper and low activation martensite/ferritic stainless steel; The middle adaptation layer that the 0.5-1 millimeter is arranged; Its starting material constitute the chrome zirconium copper alloy powder of 30-40% weight and the stainless steel powder of 60-70% weight, and middle adaptation layer is to realize the guarantee of reliable soldering between different materials; At low load region; Be welded by first wall material metal tungsten and back propping material high temperature insostatic pressing (HIP); Described back propping material is a thickness greater than low activation martensite/ferritic stainless steel of 300 millimeters, is distributed with the cooling duct therebetween, between tungsten and low activation martensite/ferritic stainless steel; The middle adaptation layer that 0.5 millimeter is arranged, its starting material constitute the tungsten powder alloyed powder of 10-20% weight and the stainless steel alloy powder of 80-90% weight.
Characteristic of the present invention also is: the shape of described first wall material metal tungsten is identical with plasma outermost magnetic surface; The shape of the low activation martensite/ferritic stainless steel of described back propping material is identical with the vacuum chamber shape; Even distribution diameter is 12 millimeters cooling duct in the described middle cooling heat sink material chromium zirconium copper, and even distribution diameter is 15 millimeters cooling duct in the low activation martensite/ferritic stainless steel of back propping material; Described high temperature insostatic pressing (HIP) welding condition is: 100-120Pa pressure, 900 degree continue 4-5 hour, in the high heat load district, cool off fast by per minute and once reduce to 350 degree, after be cooled to normal temperature 20-30 degree; Do not need quick cooling at low load region, directly be cooled to normal temperature 20-30 degree; Quick cooling after welding finishes is to guarantee that chromium zirconium copper crystal grain is constant and make the constant necessary condition of its performance, must strictly carry out in the implementation process; The raw-material alloyed powder of said adaptation layer is in isostatic, and when temperature was spent above 400, beginning was melted gradually, spends when temperature arrives 900, and whole the thawing realized effectively welding.
Advantage of the present invention is: the present invention used purity greater than 99.5%, thickness greater than the tungsten of 20mm as the first wall material; Used low activation martensite/ferritic stainless steel in the low heat loads district; The whole heat and other static pressuring processes that adopts welds; Used low activation martensite/ferritic stainless steel and chromium zirconium copper in the high heat load district, the whole sandwich structure heat and other static pressuring processes that adopts welds, stable the operating under the 350 degree conditions of whole first wall structure ability; Make the magnetic confinement reactor under the condition of fuel recycle, satisfy the requirement of the long-time steady-state operation that low material corrosion, low fuel are detained near zero delay.
Description of drawings
Fig. 1 is the structural drawing of the inner first wall material of magnetic confinement reactor.
Fig. 2 is the low load region structural representation.
Fig. 3 is a high heat load plot structure synoptic diagram.
Embodiment
A kind of structure of utilizing tungsten as the first wall material of magnetic confinement reactor; The vacuum chamber 1 of magnetic confinement reactor is divided into low load region and high heat load district by institute's affected by hot loading; Low load region comprises high field region 4 and low place 5; The high heat load district comprises divertor district 2 and 3; It is characterized in that: all vacuum chamber 1 inner first wall materials of magnetic confinement reactor all are purity greater than 99.5%, heavy wall is greater than 20 millimeters tungsten 6, and the shape of described first wall material metal tungsten 6 is identical with plasma 14 outermost magnetic surfaces, and whole first wall structure can stable operation under 350 degree conditions; In the high heat load district; Adopt first wall material metal tungsten 6 and middle cooling heat sink material and back propping material to be welded by the sandwich structure high temperature insostatic pressing (HIP); Middle cooling heat sink material is a thickness greater than 50 millimeters chromium zirconium copper 7; Back propping material is a thickness greater than low activation martensite/ferritic stainless steel 8 of 300 millimeters; The shape of the low activation martensite/ferritic stainless steel 8 of described back propping material is identical with vacuum chamber 1 shape; Be evenly distributed with diameter in the middle cooling heat sink material chromium zirconium copper 7 and be 12 millimeters cooling duct 9, back propping material hangs down that to be evenly distributed with diameter in activation martensite/ferritic stainless steel 8 be 15 millimeters cooling duct 10, and the cooling duct is convenient to remove fast from the thermal load of plasma; The middle adaptation layer 11 that 0.5 millimeter is arranged between tungsten 6 and chromium zirconium copper 7, its starting material constitute the tungsten powder alloyed powder of 10-20% weight and the chrome zirconium copper alloy powder of 80-90% weight; Between chromium zirconium copper 7 and low activation martensite/ferritic stainless steel 8; The middle adaptation layer 12 that the 0.5-1 millimeter is arranged; Its starting material constitute the chrome zirconium copper alloy powder of 30-40% weight and the stainless steel powder of 60-70% weight, and middle adaptation layer is to realize the guarantee of reliable soldering between different materials; One-piece construction is when welding; Pressure is 100-120Pa, and temperature is 900-950 degree centigrade, continues 4-5 hour; Be quickly cooled to 350 degrees centigrade by per minute speed once then; After be cooled to normal temperature 20-30 degree centigrade, the quick cooling after welding finishes is to guarantee that chromium zirconium copper crystal grain is constant and make the constant necessary condition of its performance, must strictly carry out in the implementation process; At low load region, be welded by first wall material metal tungsten 6 and back propping material high temperature insostatic pressing (HIP), described back propping material is a thickness greater than low activation martensite/ferritic stainless steel 8 of 300 millimeters; Be distributed with diameter therebetween and be 15 millimeters cooling duct 10, between tungsten 6 and low activation martensite/ferritic stainless steel 8, the middle adaptation layer 13 of 0.5 millimeter is arranged; Its starting material constitute the tungsten powder alloyed powder of 10-20% weight and the stainless steel alloy powder of 80-90% weight; One-piece construction pressure when welding is 100-120Pa, and temperature is 900-950 degree centigrade, continues 4-5 hour; Be cooled to normal temperature 20-30 degree centigrade then, need not cool off fast.The raw-material alloyed powder of above-mentioned adaptation layer is in isostatic, and when temperature was spent above 400, beginning was melted gradually, spends when temperature arrives 900, and whole the thawing realized effectively welding.
Claims (5)
1. structure of utilizing tungsten as the first wall material of magnetic confinement reactor; The vacuum chamber of magnetic confinement reactor is divided into low load region and high heat load district by institute's affected by hot loading; Low load region comprises high field region and low place; The high heat load district comprises the divertor district, it is characterized in that: all internal vacuum chamber first wall materials of magnetic confinement reactor all are purity greater than 99.5%, heavy wall is greater than 20 millimeters tungsten, and whole first wall structure can stable operation under 350 degree conditions; In the high heat load district; Adopt first wall material metal tungsten and middle cooling heat sink material and back propping material to be welded by the sandwich structure high temperature insostatic pressing (HIP); Middle cooling heat sink material is a thickness greater than 50 millimeters chromium zirconium copper; Back propping material is a thickness greater than low activation martensite/ferritic stainless steel of 300 millimeters; Middle cooling heat sink material, back propping material all are distributed with the cooling duct, and the middle adaptation layer of 0.1-0.15 millimeter is arranged between tungsten and chromium zirconium copper, and its starting material constitute the tungsten powder alloyed powder of 10-20% weight and the chrome zirconium copper alloy powder of 80-90% weight; Between chromium zirconium copper and low activation martensite/ferritic stainless steel, the middle adaptation layer of 0.1-0.15 millimeter is arranged, its starting material constitute the chrome zirconium copper alloy powder of 30-40% weight and the stainless steel powder of 60-70% weight; At low load region; Be welded by first wall material metal tungsten and back propping material high temperature insostatic pressing (HIP); Described back propping material is a thickness greater than low activation martensite/ferritic stainless steel of 300 millimeters, is distributed with the cooling duct therebetween, between tungsten and low activation martensite/ferritic stainless steel; The middle adaptation layer that 0.15 millimeter is arranged, its starting material constitute the tungsten powder alloyed powder of 10-20% weight and the stainless steel alloy powder of 80-90% weight.
2. the structure of utilizing tungsten as the first wall material of magnetic confinement reactor according to claim 1 is characterized in that: the shape of described first wall material metal tungsten is identical with plasma outermost magnetic surface; The shape of the low activation martensite/ferritic stainless steel of described back propping material is identical with the vacuum chamber shape.
3. the structure of utilizing tungsten as the first wall material of magnetic confinement reactor according to claim 1; It is characterized in that: even distribution diameter is 12 millimeters cooling duct in the described middle cooling heat sink material chromium zirconium copper, and even distribution diameter is 15 millimeters cooling duct in the low activation martensite/ferritic stainless steel of back propping material.
4. the structure of utilizing tungsten as the first wall material of magnetic confinement reactor according to claim 1; It is characterized in that: described high temperature insostatic pressing (HIP) welding condition is: 100-120Pa pressure; 900-950 degree centigrade, continue 4-5 hour, in the high heat load district; To cool off fast by per minute once reducing to 350 the degree, after be cooled to normal temperature 20-30 degree; Do not need quick cooling at low load region, directly be cooled to normal temperature 20-30 degree.
5. the structure of utilizing tungsten as the first wall material of magnetic confinement reactor according to claim 1; It is characterized in that: the raw-material alloyed powder of said adaptation layer is in isostatic; When temperature was spent above 400, beginning was melted gradually, when temperature arrives 900 degree; All melt, realize effectively welding.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012100696748A CN102610285A (en) | 2012-03-16 | 2012-03-16 | Structure utilizing metal tungsten as first wall material of magnetic confinement reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012100696748A CN102610285A (en) | 2012-03-16 | 2012-03-16 | Structure utilizing metal tungsten as first wall material of magnetic confinement reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN102610285A true CN102610285A (en) | 2012-07-25 |
Family
ID=46527597
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2012100696748A Pending CN102610285A (en) | 2012-03-16 | 2012-03-16 | Structure utilizing metal tungsten as first wall material of magnetic confinement reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN102610285A (en) |
Cited By (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103331517A (en) * | 2013-06-20 | 2013-10-02 | 安泰科技股份有限公司 | Tungsten-base heavy alloy hot isostatic pressing diffusion connecting welding method |
| CN103886919A (en) * | 2014-03-26 | 2014-06-25 | 北京工业大学 | Method for improving fusion reactor inner wall plasma irradiation prevention performance through lamination |
| CN104021820A (en) * | 2014-06-05 | 2014-09-03 | 中国科学院等离子体物理研究所 | High-accuracy quick assembling and disassembling structure for tokamak divertor module |
| CN104157311A (en) * | 2014-08-19 | 2014-11-19 | 中国工程物理研究院核物理与化学研究所 | Thin-wall fusion target chamber for Z-pinch driven fusion-fission hybrid power reactor |
| CN104409108A (en) * | 2014-12-17 | 2015-03-11 | 中国科学院合肥物质科学研究院 | Dual-layer-flow liquid first wall cladding applicable to magnetic confinement fusion reactor |
| CN105679380A (en) * | 2016-01-11 | 2016-06-15 | 王傑 | Room temperature hydrogen capture type neutron nuclear fusion-ignited self-holding chain type hydrogen reactor |
| CN107507651A (en) * | 2017-08-15 | 2017-12-22 | 中国科学院合肥物质科学研究院 | A kind of double cold loop Divertor structures suitable for following Tokamak Fusion Reactor |
| CN109961854A (en) * | 2017-12-25 | 2019-07-02 | 哈尔滨工业大学 | A kind of nuclear fusion first pars intramuralis cooling duct cooling based on jet stream |
| CN109961856A (en) * | 2017-12-25 | 2019-07-02 | 哈尔滨工业大学 | It is a kind of to prevent from facing excessively high the first wall of nuclear fusion of plasma part temperature directly |
| CN110428912A (en) * | 2019-08-02 | 2019-11-08 | 太原理工大学 | Plasma facing material and preparation method thereof containing diamond |
| CN110739087A (en) * | 2019-10-22 | 2020-01-31 | 中国科学院合肥物质科学研究院 | box body opening structure suitable for independent teleoperation of divertor wall |
| CN111415761A (en) * | 2019-01-07 | 2020-07-14 | 新奥科技发展有限公司 | Plasma-oriented part and fusion device |
| CN115216720A (en) * | 2022-06-13 | 2022-10-21 | 深圳大学 | Tungsten composite coating applied to first wall of cladding of nuclear fusion device and preparation method thereof |
| CN116189927A (en) * | 2023-04-25 | 2023-05-30 | 中国科学院合肥物质科学研究院 | Particle recycling control system and method capable of meeting kilosecond plasma operation |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH05256968A (en) * | 1992-03-13 | 1993-10-08 | Hitachi Ltd | First wall of fusion reactor |
| JPH11190787A (en) * | 1997-12-26 | 1999-07-13 | Japan Atom Energy Res Inst | Heat resistant direct joint structure of high melting point material and high thermal conductivity material or jointing method therefor |
| EP1063871A1 (en) * | 1999-06-24 | 2000-12-27 | European Community | Divertorfiltering element for a tokamak nuclear fusion reactor, divertor employing the filtering element and tokamak nuclear fusion reactor employing the divertor |
| CN1538462A (en) * | 2003-04-02 | 2004-10-20 | �����ɷ� | Lameller component of fusion reactor |
| CN1755840A (en) * | 2005-10-27 | 2006-04-05 | 中国科学院等离子体物理研究所 | Be coated with the first wall parts of thick tungsten coating or low activation steel heat sink material and preparation method thereof |
| CN101013610A (en) * | 2007-01-29 | 2007-08-08 | 中国科学院等离子体物理研究所 | Cool-off heat sink of steady-state tokamak divertor |
| CN101048826A (en) * | 2004-10-27 | 2007-10-03 | 普兰西欧洲股份公司 | Single board cooling device component |
-
2012
- 2012-03-16 CN CN2012100696748A patent/CN102610285A/en active Pending
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH05256968A (en) * | 1992-03-13 | 1993-10-08 | Hitachi Ltd | First wall of fusion reactor |
| JPH11190787A (en) * | 1997-12-26 | 1999-07-13 | Japan Atom Energy Res Inst | Heat resistant direct joint structure of high melting point material and high thermal conductivity material or jointing method therefor |
| EP1063871A1 (en) * | 1999-06-24 | 2000-12-27 | European Community | Divertorfiltering element for a tokamak nuclear fusion reactor, divertor employing the filtering element and tokamak nuclear fusion reactor employing the divertor |
| CN1538462A (en) * | 2003-04-02 | 2004-10-20 | �����ɷ� | Lameller component of fusion reactor |
| CN101048826A (en) * | 2004-10-27 | 2007-10-03 | 普兰西欧洲股份公司 | Single board cooling device component |
| CN1755840A (en) * | 2005-10-27 | 2006-04-05 | 中国科学院等离子体物理研究所 | Be coated with the first wall parts of thick tungsten coating or low activation steel heat sink material and preparation method thereof |
| CN101013610A (en) * | 2007-01-29 | 2007-08-08 | 中国科学院等离子体物理研究所 | Cool-off heat sink of steady-state tokamak divertor |
Cited By (24)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103331517A (en) * | 2013-06-20 | 2013-10-02 | 安泰科技股份有限公司 | Tungsten-base heavy alloy hot isostatic pressing diffusion connecting welding method |
| CN103331517B (en) * | 2013-06-20 | 2016-01-20 | 安泰科技股份有限公司 | A kind of tungsten Heavy Alloys high temperature insostatic pressing (HIP) diffusion connects the method for weldering |
| CN103886919A (en) * | 2014-03-26 | 2014-06-25 | 北京工业大学 | Method for improving fusion reactor inner wall plasma irradiation prevention performance through lamination |
| CN103886919B (en) * | 2014-03-26 | 2016-02-17 | 北京工业大学 | Lamination is utilized to improve the method for fusion reactor inwall anti-plasma irradiation behaviour |
| CN104021820A (en) * | 2014-06-05 | 2014-09-03 | 中国科学院等离子体物理研究所 | High-accuracy quick assembling and disassembling structure for tokamak divertor module |
| CN104021820B (en) * | 2014-06-05 | 2016-09-28 | 中国科学院等离子体物理研究所 | A kind of Tokamak divertor module high accuracy Quick assembling-disassembling structure |
| CN104157311A (en) * | 2014-08-19 | 2014-11-19 | 中国工程物理研究院核物理与化学研究所 | Thin-wall fusion target chamber for Z-pinch driven fusion-fission hybrid power reactor |
| CN104157311B (en) * | 2014-08-19 | 2016-12-07 | 中国工程物理研究院核物理与化学研究所 | A kind of thin-walled fusion target chamber for Z constriction Fusion-fission energy mix heap |
| CN104409108A (en) * | 2014-12-17 | 2015-03-11 | 中国科学院合肥物质科学研究院 | Dual-layer-flow liquid first wall cladding applicable to magnetic confinement fusion reactor |
| CN104409108B (en) * | 2014-12-17 | 2017-01-18 | 中国科学院合肥物质科学研究院 | Dual-layer-flow liquid first wall cladding applicable to magnetic confinement fusion reactor |
| CN105679380A (en) * | 2016-01-11 | 2016-06-15 | 王傑 | Room temperature hydrogen capture type neutron nuclear fusion-ignited self-holding chain type hydrogen reactor |
| CN107507651B (en) * | 2017-08-15 | 2019-05-31 | 中国科学院合肥物质科学研究院 | A kind of double cold loop Divertor structures suitable for Tokamak Fusion Reactor |
| CN107507651A (en) * | 2017-08-15 | 2017-12-22 | 中国科学院合肥物质科学研究院 | A kind of double cold loop Divertor structures suitable for following Tokamak Fusion Reactor |
| CN109961854A (en) * | 2017-12-25 | 2019-07-02 | 哈尔滨工业大学 | A kind of nuclear fusion first pars intramuralis cooling duct cooling based on jet stream |
| CN109961856A (en) * | 2017-12-25 | 2019-07-02 | 哈尔滨工业大学 | It is a kind of to prevent from facing excessively high the first wall of nuclear fusion of plasma part temperature directly |
| CN109961854B (en) * | 2017-12-25 | 2020-11-13 | 哈尔滨工业大学 | Internal cooling channel of first wall of nuclear fusion based on jet cooling |
| CN111415761A (en) * | 2019-01-07 | 2020-07-14 | 新奥科技发展有限公司 | Plasma-oriented part and fusion device |
| CN111415761B (en) * | 2019-01-07 | 2022-03-11 | 新奥科技发展有限公司 | Plasma-oriented part and fusion device |
| CN110428912A (en) * | 2019-08-02 | 2019-11-08 | 太原理工大学 | Plasma facing material and preparation method thereof containing diamond |
| CN110428912B (en) * | 2019-08-02 | 2020-11-03 | 太原理工大学 | First wall material containing diamond and preparation method thereof |
| CN110739087A (en) * | 2019-10-22 | 2020-01-31 | 中国科学院合肥物质科学研究院 | box body opening structure suitable for independent teleoperation of divertor wall |
| CN110739087B (en) * | 2019-10-22 | 2021-05-28 | 中国科学院合肥物质科学研究院 | Box body opening structure suitable for independent teleoperation of first wall of divertor |
| CN115216720A (en) * | 2022-06-13 | 2022-10-21 | 深圳大学 | Tungsten composite coating applied to first wall of cladding of nuclear fusion device and preparation method thereof |
| CN116189927A (en) * | 2023-04-25 | 2023-05-30 | 中国科学院合肥物质科学研究院 | Particle recycling control system and method capable of meeting kilosecond plasma operation |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN102610285A (en) | Structure utilizing metal tungsten as first wall material of magnetic confinement reactor | |
| Huang et al. | Status and strategy of fusion materials development in China | |
| EP3170181B1 (en) | Shielding materials for fusion reactors | |
| Li-Puma et al. | Potential and limits of water cooled divertor concepts based on monoblock design as possible candidates for a DEMO reactor | |
| CN105177262B (en) | A kind of method for improving special grain boundary ratio in precipitation strength austenitic heat-resistance steel | |
| CN108615563B (en) | Divertor water-cooling module of fusion device and divertor cooling target plate structure applied by divertor water-cooling module | |
| RU2546971C2 (en) | Fuel rod and method of making pellets for said fuel rod | |
| KR101332730B1 (en) | Macrostructured plate fuel element | |
| CN100510134C (en) | Nodular corrosion resistant modified Zr-4 alloy and method for making same | |
| US20120314831A1 (en) | Light Water Reactor TRISO Particle-Metal-Matrix Composite Fuel | |
| US20190139654A1 (en) | High temperature nuclear fuel system for thermal neutron reactors | |
| CN111933313B (en) | Long-life neutron absorption material | |
| Antusch et al. | Refractory materials for energy applications | |
| CN109576534A (en) | A kind of low W content γ ` phase strengthens cobalt base superalloy and its preparation process | |
| CN110415838A (en) | A kind of rodlike nuclear fuel element and preparation method thereof enhancing safety | |
| Šmid et al. | Lifetime of Be-, CFC-and W-armoured ITER divertor plates | |
| CN101440446A (en) | Industrial lithium-lead alloy | |
| Duan et al. | Progress in fusion technology at SWIP | |
| Lyublinski et al. | Module of lithium divertor for KTM tokamak | |
| Li et al. | Optimization of the chamfering structures for ITER-like W/Cu monoblocks to avoid the leading edge-induced melting in EAST | |
| KR20050059282A (en) | Fuel pellet for a nuclear reactor and method for the production thereof | |
| Schlosser et al. | Design, fabrication and testing of an improved high heat flux element, experience feedback on steady state plasma facing components in Tore Supra | |
| CN102087946A (en) | Structure for improving heating efficiency of cathode heater assembly and preparation method thereof | |
| Burkes et al. | An Overview of Current and Past W-UO [2] CERMET Fuel Fabrication Technology | |
| Apicella et al. | Preliminary analysis on a liquid lithium limiter in capillary porous system (CPS) configuration in view of a “litization” experiment on FTU tokamak |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C12 | Rejection of a patent application after its publication | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20120725 |