等离子体杂质
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由于使用低Z涂层材料可使传统的结构材料和技术保持不变并能降低等离子体杂质,因而为设计提供了灵活性。
Because of using low Z coating materials , the conventional first wall construction materials and techniques can be retained and plasma impurity levels can be reduced .
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对HL-1M装置的硅化涂层性能以及对等离子体杂质、热辐射和再循环进行了研究,并对装置抽气扁管内壁状态进行了分析描述。
In this paper , the performances of siliconized film on the first wall , and the effect on impurities and radiation in HL-1M Tokamak are described .
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本文叙述了用真空紫外光谱方法观测HL-1装置常规、器壁碳化和抽气孔栏三种放电条件下等离子体杂质的变化以及某些杂质的特性。
Some properties of the impurity in the HL-1 tokamak are studied by the VUV spectroscopic method under different discharge conditions : regular , With wall carbonization and with a pumping limiter .
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本文介绍了HL-1M装置等离子体杂质真空紫外辐射观测的初步结果。
The results of impurity VUV radiation observation on the HL 1M device are given in this paper .
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HL-1M托卡马克脉冲超声分子束注入等离子体及杂质特性研究
The plasma and impurity characteristics with pulsed molecular beam injection in the HL 1M Tokamak
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聚变等离子体中杂质碳的辐射损失
Radiative loss for carbon plasma impurity
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用钛吸气方法减少了HL-1托卡马克等离子体中的杂质和气体再循环率,使Z(eff)降低到1.6;
Titanium gettering has been used in the HL-1 tokamak as a means to reduce impurity radiation and to expand the parameter space of operation .
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分析和研究了等离子体光谱,杂质成分、杂质来源和等离子体喷枪的发射机制。
The plasma spectra , impurities , impurity sources and radiation mechanism of plasma gun are analysed .
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在托卡马克运行过程中,其内部的等离子体中的杂质会引起大量的辐射损失,制约所能获得的等离子体的品质,影响托卡马克高参数、准稳态运行。
The impurities in plasma cause lot of radiation loss , which limits the quality of the plasma and affects the high-quality and quasi-steady-state operation of Tokamak .
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借助数值分析了α粒子能量利用及分配、束注入特性、等离子体约束、杂质和初边条件对结果的影响,可供设计准稳态热核堆芯时参考。
Conditions which affect the results were analysed . These include energy utilization , distribution of α - particles , injection characteristics , confinement and impurity of plasma , initial and boundary conditions , etc.
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HL-1装置脱离等离子体及边界等离子体杂质辐射的观测
Observation of detached plasma and impurity radiations at the boundary of the HL-1 plasma
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托卡马克等离子体边缘梯度和杂质辐射驱动的湍流理论
Theory of turbulence driven by edge gradients and impurity radiation in tokamaks
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弹丸注入是聚变工程和实验中研究等离子体加料、控制等离子体密度和杂质的重要手段。
Pellet injection is an important way for plasma fuelling 、 plasma density and impurity control in fusion engineering and experimental research .
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杂质输运的数值模拟结果说明,无论在通常欧姆等离子体中,还是在偏压诱发H模等离子体中,杂质的输运系数都比新经典理论预计的要大得多,输运是反常的。
The impurity transport simulation results indicate that in both the normal Ohmic plasma and the H mode plasma induced by a biasing electrode , compared with neoclassical theory , the impurity transport coefficient is so high that the impurity transport is anomalous .
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利用光谱仪对托卡马克内部等离子体的发射光谱进行诊断,是研究托卡马克等离子体芯部杂质输运的重要手段。
Spectrometer is an important tool to study the impurities transportation in the plasma .
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这些结果对估计面对等离子体的部件寿命和分析聚变堆堆芯等离子体中的杂质水平估计是很有用的。
These data might be useful to estimate the lifetime of plasma facing components and to analyze the impurity level in core plasma of fusion reactors .