Conveners
EXP/1 fusion devices
- Sebastijan Brezinsek
EXP/1 fusion devices
- Sebastijan Brezinsek (Forschungszentrum Jülich)
EXP/1 fusion devices
- Sebastijan Brezinsek
EXP/1 fusion devices: Summary
- Sebastijan Brezinsek
Description
Experiments 1: tokamaks, linear plasmas, stellarators
Erosion of the ITER main chamber first wall (FW) beryllium (Be) armour is expected to affect the lifetime of FW panel, dust formation, and release of Be impurities potentially leading to enhanced sputtering of the W divertor and tritium retention due to co-deposition. The ITER FW panels are shaped to protect leading edges and misalignments, which leads to magnetically shadowed regions, where...
Fulcher Bands of the hydrogenic molecular spectra are complex triplet bands in the visible region (590-630 nm). The electronic transition is identified as d (3p$^3$Π$_u$) at approximately 14 eV level energy to a (2s$^3$Σ$^+_g$) at 12 eV, but this is not the sole electronic transition in this region, as the g→c (3d $^3$Σ$^+_g$ → 2p$^3$Π$_u$) transition is present in this wavelength region as...
Upper and lower graphite divertors in EAST tokamak were replaced by tungsten divertors in 2014 and 2021, respectively, to improve plasma performance in long pulse discharges and accumulate knowledges on the tungsten divertor operation. Studies on the tungsten behavior in edge and core plasmas are then crucially important for improving the plasma performance. For the purpose four...
Thailand is one of the countries that recognizes the importance of fusion technology and has a national plan for its implementation. The Thailand Institute of Nuclear Technology (TINT) has been engaged in the development of a tokamak device known as Thailand Tokamak-1 (TT-1) since 2015. This device is derived from the HT-6M, a previous tokamak device developed by the Chinese Academy of Science...
The Pakistan Spherical Tokamak (PST) is a small-sized spherical tokamak currently in the design and development phase. A double null divertor configuration is being considered for the steady-state operation of the PST. Two different divertor materials concepts are under consideration for the PST and other devices in the future. The interaction between plasma and tungsten surfaces leads to...
• Egyptian Atomic Energy Authority – Plasma Focus device 1 (EAEA-PF1) was successfully redesigned in terms of its electrode system material and dimensions, insulator shape and the energy storage bank to investigate the best plasma focus action.
• A simple-to-perform technique was applied to investigate the distribution of the azimuthal magnetic field induction and the induced magnetic force...
Hydrogen glow discharge cleaning (H-GDC) is a routine conditioning procedure for the present tokamaks and the future fusion machines, including the ITER. Due to the low energy of hydrogen ions in glow discharge plasmas, the probability of any considerable damage to the plasma facing components was mainly ignored among researchers in the field. In this work, Tungsten and Molybdenum, as the...
