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The Oxidation Behavior of Vanadium Alloys in Air at Elevated Temperature

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Southwestern Institute of Physics Annual Report 2001年第1期 61-64页

作者： CHENJiming XUYing xuzengyu

Vanadium alloy is one of the most important candidate structural materials for a fusion reactor. Its main advantages over other candidates are its low activity feature and feasible properties at high temperature. However, vanadium is easily oxidized at high temperature to form a non-protective surface film of V2O5. Oxygen concentration would thus get high and the properties get worse in not only the loss of the ductility but also the enhanced hydrogen embrittlement by the oxidation.

关键词：钒合金氧化反应氧化温度放射性特征

MHD Instability Analysis of Liquid Metal Free Surface Jet Flow in Non-Uniform Magnetic Fields

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Southwestern Institute of Physics Annual Report 2002年第1期 54-57页

作者： xuzengyu KANGWeishan PANChuanjie

In order to solve the magneto-hydrodyna-mics(MHD) problems, it is neccessary to combine Maxwell's equations with fluid mechanics equations. But, under the first order approximation the mass point motivation equations ... 详细信息

关键词： MHD 不稳定性喷气流流体力学麦克斯韦方程

The Brittle Fracture Mechanism of Vanadium Alloy with High Level of Oxygen and Hydrogen

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Southwestern Institute of Physics Annual Report 2001年第1期 51-55页

作者： CHENJiming xuzengyu YANGLin LIUXiang

Hydrogen embrittlement is one of the key issues for the vanadium alloys for fusion application. Previous study has shown that V4Ti alloy had better properties against the embrittlement than V4Cr4Ti and V4Ti3A1 alloys. It was thought that the better property was benefited from the small ratio of itsyield strength over its ultimate tensilestrength.

关键词：钒合金氢脆变钛合金断裂装置

Experimental Study on the Resistance to Hydrogen Embrittlement of NIFS-V4Cr4Ti Alloy

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Southwestern Institute of Physics Annual Report 2001年第1期 55-57页

作者： CHENJiming xuzengyu T.Muroga DENYing 不详 JapanNationalInstituteofFusionScience

There are more and more countries to ake an effort to the studies of vanadium alloy for fusion application. NIFS in Japan has recently developed an 80 kg heat V4Cr4Ti alloy (NIFS-heat 2) after the production of a 500 kg scale V4Cr4Ti in U. S. several years ago. Property evaluation of the alloy has beenput into an international collaboration program under the coordination of IEA (International Energy Agency). SWIP has joined the collabration on the hydrogen embrittlement resistance evaluation of the alloyt.

关键词：钒合金氢脆变阻抗 NIFS

Development of New Type Multi-Elements Doped Carbon-Base Plasma Facing Materials

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Southwestern Institute of Physics Annual Report 2002年第1期 52-54页

作者： xuzengyu LIUXiang CHENJiming WANGMingxu SONGJinren ZHAIGengtai LIChengxin 不详 InstituteofCoalChemistry ChineseAcademyofScienceTaiyuan300010 TheFirstInstituteofSpaceScience＆Technologv CorporateBeijing100076

Carbon-base materials will be major plasma facing materials (PFM) in a fusion device in near term and even in the future in spite of its high tritium trapping and chemical sputtering yield. Of course, the development ... 详细信息

关键词：多元素掺杂碳基等离子体防面材料辐射增强升华核聚变反应堆

Microstructure and Texture Changes of Tungsten-Rhenium coated on Carbon Fiber Composite during Annealing

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Southwestern Institute of Physics Annual Report 2002年第1期 66-69页

作者： LIUXiang xuzengyu S.Tamura N.Yoshida 不详 ResearchInstituteforAppliedMechanics KyushuUniversity6-1KasugakoenKasugaFukuoka816-8580Japan

Since tungsten was chose as the divertor tiles of 1TER, the investigation of tungsten and its coating as plasma facing material (PFM) have been paid more attentions by fusion scientists all over the world. Recent year... 详细信息

关键词：钨-铹镀层微观结构碳素纤维退火处理等离子体防面材料聚变反应堆

The Erosion and Erosion Products of Tungsten and Carbon Based Materials Bombarded by High Energy Pulse Electron Beam

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Southwestern Institute of Physics Annual Report 2001年第1期 47-51页

作者： LIUXiang N.Yoshida N.Noda ZHANGFu xuzengyu LIUYong 不详 ResearchInstituteforAppliedMechanics KyushuUniversity6-1KasugakoenKasugaFukuoka816-8580Japan NationalInstituteforFusionScience TokiGifu509-5292Japan

High Z and low Z materials are both the candidate plasma facing materials (PFM), up to now, the typical representative of high Z materials is tungsten, and the representatives of low Z materials are carbon materials (such as graphite, C/C composite) and beryllium. Most of these materials have been used as PFM limiters and diverter armor tiles of tokamak machines, tungsten, molybdenum and C/C composite are always used as high heat flux components.

关键词：热侵蚀腐蚀品碳基原料高能脉冲电子束等离子体表面材料

Development of High Quality Tungsten Coating as Plasma Facing Materials and Components

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Southwestern Institute of Physics Annual Report 2002年第1期 57-61页

作者： LIUXiang xuzengyu LIUYong GEChangchun S.Tamura N.Yoshida 不详 BeijingScienceandTechnologyUniversity Beijing ResearchInstituteofAppliedMechanics KyushuUniversityJapan

The control of core plasma and impurity level of edge plasma has been greatly improved with the development of controlled fusion technology. Refractory metal tungsten or its alloy was paid more attentions owing to its... 详细信息

关键词：钨镀层等离子体防面材料聚变控制 CVD 热力匹配

The Recovery and Recrystallization of the Cold Rolled V-W-Ti Alloys

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Southwestern Institute of Physics Annual Report 2002年第1期 61-65页

作者： CHENJiming T.Muroga T.Nagasaka1 XUYing xuzengyu 不详 NationalInstituteforFusionScience OroshiTokiGifu509-5292Japan

Vanadium alloys, especially that of V4Cr4Ti, are supposed as the promising candidate structural material for fusion applications for their good thermal properties, high temperature strength and the inherent low activa... 详细信息

关键词：再结晶冷轧铅合金回收再生结构材料核聚变防护