Development to new stage of helical plasma confinement

螺旋等离子体约束发展到新阶段

• 批准号: 11694108
• 负责人: MATSUOKA Keisuke
• 金额: $ 1.86万
• 依托单位: Natiomal Institute for Fusion Science(NIFS)
• 依托单位国家: 日本
• 项目类别: Grant-in-Aid for Scientific Research (B).
• 财政年份: 1999
• 资助国家: 日本
• 起止时间: 1999 至 无数据
• 项目状态: 已结题
• 来源: https://kaken.nii.ac.jp/en/grant/KAKENHI-PROJECT-11694108/
• 关键词: Helical plasma; quasi-axisymmetry; non-circularity; high ino temperature; omnigeity; high electron temperature mode; potential bifurcation; HIBP

1) Progress has been made on physics and engineering design of CHS-qa, which is supposed to be a post-CHS device. Stability β up to 4% and good orbit confinement of high energy ions have been achieved. High performance results in high elongation of plasma cross-section. 2) Ion thermal diffusivity of high ion temperature mode of CHS plasma has been estimated by using the effective helical ripple of the neoclassical theory. The estimated values are close to the experimental one. The ion diffusivity for quasi-omnigenous configuration realized by a strong inward shift of the magnetic axis, where the bottom of helical ripple has the same magnetic field strength, has been estimated. The expected ion temperature for the quasi-omnigenous configuration is 1.5keV, which is much higher than the value obtained so far in high Ti mode of 1keV. 3) Confinement improvement of electron results from the potential bifurcation in CHS, which leads to the high electron temperature mode where high central electron temperature of 2keV is realized. The same phenomenon of the internal transport barrier has been observed in T-10 tokamak. The transport barrier is formed at the position where the radial electric field shear is strong for both plasmas (CHS and T-10). 4) Qualitative explanation has been made on the fact that the equilibrium βvalue increases as the elongation of plasma cross-section increases. The elongation should play a role in getting a high performance plasma. It is shown that magnetic measurements can not determine uniquely the current and pressure profiles of toroidal plasmas.

1)作为后CHS装置的CHS-QA在物理和工程设计方面取得了进展。实现了高能离子的稳定性β达4%和良好的轨道约束。高性能导致了等离子体截面的高延伸率。2)利用新经典理论的有效螺旋波纹，估算了CHS等离子体高离子温度模的离子热扩散率。估计值与实验值接近。对螺旋波底部具有相同磁场强度的磁轴强烈内移所实现的准全向位形的离子扩散率进行了估算。准全能组态的预期离子温度为1.5keV，远高于迄今在1keV的高钛模式下所得到的温度。3)CHS势能分叉导致电子中心温度高达2keV，从而改善了电子的禁闭性能。在T-10托卡马克上也观察到了同样的内部输运势垒现象。输运势垒是在两个等离子体(CHS和T-10)的径向电场剪切较强的位置形成的。4)定性地解释了平衡β值随等离子体截面伸长率的增大而增大的现象。延伸率应该在获得高性能等离子体中发挥作用。结果表明，磁测量不能唯一地确定环形等离子体的电流和压力分布。

项目成果

V.D.Pustofitov: "Plasma Shape Control and Equilibrium Bata Limit in Conventional Stellarations"Journal of Plasma and Fusion Reseach SERIES. 3. (2000)

V.D.Pustofitov：“常规恒星中的等离子体形状控制和平衡巴塔极限”等离子体与聚变研究系列杂志。

V.D.Pustofitov: "Magnetic diagnostics: general principles and the problem of reconstruction of plasma current and pressure profiles"Nuclear Fusion. 40. (2000)

V.D.Pustofitov：“磁诊断：等离子体电流和压力分布的一般原理和重建问题”核聚变。

O. S. Parlichenko et al.: "Ion Thermal Diffusivity in High Ion Temperature Mode in CHS"Plasma Physics and Controlled Fusion. 42. (2000)

O. S. Parlichenko 等人：“CHS 中高离子温度模式下的离子热扩散率”等离子体物理和受控聚变。

O.S.Pavlichenko et al.: "Ion Thermal Diffusivity in High Ion Temperature Mode in CHS"Plasma Physics and Controlled Fusion. 42. (2000)

O.S.Pavlichenko 等人：“CHS 中高离子温度模式下的离子热扩散率”等离子体物理和受控聚变。

S.Okamura et al.: "Low-aspect -ratio Quasi-axisymmetric Stellarator CHS-qa"Journal of Plasma and Fusion Research S ERIES. Vol. 3. (2000)

S.Okamura 等人：“低纵横比准轴对称仿星器 CHS-qa”等离子体与聚变研究系列期刊。