Berzak L, Kaita R, Kozub T, Majeski R, Zakharov L
Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton, New Jersey 08543, USA.
Rev Sci Instrum. 2008 Oct;79(10):10F116. doi: 10.1063/1.2955567.
The lithium tokamak experiment (LTX) is a spherical tokamak with R(0)=0.4 m, a=0.26 m, B(TF) approximately 3.4 kG, I(P) approximately 400 kA, and pulse length approximately 0.25 s. The focus of LTX is to investigate the novel low-recycling lithium wall operating regime for magnetically confined plasmas. This regime is reached by placing an in-vessel shell conformal to the plasma last closed flux surface. The shell is heated and then coated with liquid lithium. An extensive array of magnetic diagnostics is available to characterize the experiment, including 80 Mirnov coils (single and double axis, internal and external to the shell), 34 flux loops, 3 Rogowskii coils, and a diamagnetic loop. Diagnostics are specifically located to account for the presence of a secondary conducting surface and engineered to withstand both high temperatures and incidental contact with liquid lithium. The diagnostic set is therefore fabricated from robust materials with heat and lithium resistance and is designed for electrical isolation from the shell and to provide the data required for highly constrained equilibrium reconstructions.
锂托卡马克实验（LTX）是一个球形托卡马克，其R(0)=0.4米，a=0.26米，B(TF)约为3.4千高斯，I(P)约为400千安，脉冲长度约为0.25秒。LTX的重点是研究磁约束等离子体的新型低再循环锂壁运行模式。通过放置一个与等离子体最后封闭磁通表面共形的容器内壳来实现这种模式。对内壳进行加热，然后涂上液态锂。有一系列广泛的磁诊断设备可用于表征该实验，包括80个米尔诺夫线圈（单轴和双轴，壳体内外）、34个磁通环、3个罗果夫斯基线圈和一个抗磁环。诊断设备的位置经过专门设计，以考虑到二次导电表面的存在，并经过精心设计，能够承受高温以及与液态锂的偶然接触。因此，诊断设备由具有耐热性和耐锂性的坚固材料制成，设计用于与外壳进行电气隔离，并提供高度受限的平衡重建所需的数据。
