Characteristics of High Z Materials as A plasma Facing Material

高 Z 材料作为等离子体表面材料的特性

• 批准号: 05452395
• 负责人: TANABE Tetsuo
• 金额: $ 4.42万
• 依托单位: Osaka University
• 依托单位国家: 日本
• 项目类别: Grant-in-Aid for General Scientific Research (B)
• 财政年份: 1993
• 资助国家: 日本
• 起止时间: 1993 至 1994
• 项目状态: 已结题
• 来源: https://kaken.nii.ac.jp/en/grant/KAKENHI-PROJECT-05452395/
• 关键词: Molybdenum; Tungsten; Plasma Facing Material; Atomic Hydrogen; Hydrogen Ion; Therma Shock Resistance; Plasma-Wall Interacitons; Hydrogen Recycling

(1) Hydrogen diffusion and permeation study has been done with using a gaseous charging method and both coefficients of diffusion and diffusion are precisely determined.(2) With using hydrogen atoms, hydrogen reflection and retention as well as permeation and diffusion, have also been studied. Refferring high energy hydrogen injection, hydrogen recycling properties of high Z metals are analyzed in detail for future use of the high Z in a fusion reactor.(3) Halpha emission from reflected hydrogen atom under energetic hydrogen ion bombardment is analyzed. From Doppler-shift and -broadening detailed mechanism of the Halpha emission is determined.(4) High Z (Mo and W) limiter test has been carried out in TEXTOR,which is a medium size tokamak plasma experimental apparatus at KFA,Julich in Germany. Various subjects, such as, the release of high Z impurity from the limiter, the influence of high Z impurities on main plasma, the behavior of high Z impurities in scrape-off plasma and so on, have been examined. And the results are analyzed by many scientists internationally under an IEA contract. Various new and informative results are now beeing produced for the utilization of high Z materials as a plasma facing material.

(1)用充气法研究了氢的扩散和渗透，精确地测定了扩散系数和扩散系数。(2)利用氢原子研究了氢的反射和滞留以及渗透和扩散。针对高能氢注入，详细分析了高Z金属的氢循环特性，为高Z金属在聚变堆中的应用提供了依据。(3)分析了高能氢离子轰击下反射氢原子的α辐射。从多普勒频移和展宽的详细机制的H α发射的确定。(4)在德国KFA的中型托卡马克等离子体实验装置TEXTOR上进行了高Z（Mo和W）限制器试验。研究了高Z杂质从限制器中的释放、高Z杂质对主等离子体的影响、高Z杂质在刮除等离子体中的行为等问题。根据国际能源署的合同，国际上许多科学家对结果进行了分析。各种新的和翔实的结果，现在beeing产生的利用高Z材料作为等离子体面临的材料。

项目成果

V.Philipps et al.: "Molybdenum Test-Limiter Experiments in TEXTOR" J.Nucl.Fusion. 34. 1417-1429 (1994)

V.Philipps 等人：“TEXTOR 中的钼测试限制器实验”J.Nucl.Fusion。

V.Philipps et al.: "Molybdenum Test-Limiter Expereiments in TEXTOR" J.Nucl.Fusion. 34. 1417-1429 (1994)

V.Philipps 等人：“TEXTOR 中的钼测试限制器实验”J.Nucl.Fusion。

S.Sekine et al.: "Energy Distribution of Deuterium Atoms Recycling on Molybdenum Limiter Surface" J.Nucl.Mater.(印刷中).

S. Sekine 等人：“钼限制器表面上的氘原子回收的能量分布”J. Nucl。

K.Niwase et al.: "Dislocation Loops and Their Depth Profilies in He^+ and D^+ Ion Irradiation" J.Nucl.Mater.203. 56-66 (1993)

K.Niwase 等人：“He^ 和 D^ 离子辐照中的位错环及其深度剖面”J.Nucl.Mater.203。

T.Tanabe et al.: "Hydrogen Reflection and Halpha Emission" J.Nucl.Mater.(In Press).

T.Tanabe 等人：“氢反射和 Halpha 发射”J.Nucl.Mater.（​​正在出版）。