A5101631237- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Laser-induced spectroscopy and plasma
- Plasma Diagnostics and Applications
- Metal and Thin Film Mechanics
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Ion-surface interactions and analysis
- Microgrid Control and Optimization
- Optimal Power Flow Distribution
- Atomic and Molecular Physics
- Photovoltaic Systems and Sustainability
- Hydrogen Storage and Materials
Chinese Academy of Sciences
2014-2019
Institute of Plasma Physics
2014-2019
University of Science and Technology of China
2016
To facilitate long-pulse high power operation, an ITER-like actively cooled tungsten (W) divertor was installed in Experimental Advanced Superconducting Tokamak (EAST) to replace the original upper graphite 2014. A dedicated multichannel visible spectroscopic diagnostic system has been accordingly developed for characterization of plasma and impurities W divertor. An array 22 lines-of-sight (LOSs) provides a profile measurement light emitted from along outer divertor, other 17 vertical LOSs...
The ITER beryllium (Be) first wall (FW) panels are shaped to protect leading edges between neighbouring arising from assembly tolerances. This departure a perfectly cylindrical surface automatically leads magnetically shadowed regions where eroded Be can be re-deposited, together with co-deposition of tritium fuel. To provide benchmark for series erosion/re-deposition simulation studies performed the FW panels, dedicated experiments have been on EAST tokamak using specially designed,...
Post-mortem methods cannot fulfill the requirement of monitoring lifetime plasma facing components (PFC) and measuring tritium inventory for safety evaluation. Laser-induced breakdown spectroscopy (LIBS) is proposed as a promising method in situ study fuel retention impurity deposition tokamak. In this study, an LIBS system was successfully established on EAST to investigate first wall without need removal tiles between discharges. Spectral lines D, H impurities (Mo, Li, Si, ... )...
Tungsten erosion and re-deposition at the upper outer divertor of Experimental Advanced Superconducting Tokamak has been modelled using 3D Monte Carlo code ERO. The measured plasma condition in attached L mode discharges with single null configuration used to build background simulations. tungsten gross rate is mainly determined by carbon impurity plasma. Increasing concentration can first increase afterwards suppress rate. Taking into account material mixing surface model, influence eroded...
To investigate the radiative divertor behavior and physics for scenario of impurity seeded plasma in ITER, experiments with argon (Ar) seeding under ITER-like tungsten condition were carried out during recent EAST campaigns. The experimental results reveal high efficiency reducing heat load particle flux onto targets owing to increased radiation by Ar seeding. We achieve detached plasmas these experiments. inner–outer asymmetry reduces after Impurities, such as Ar, C, Li, W, exist entire...
Application of lithium (Li) or silicon (Si) wall coating in the Experimental Advanced Superconducting Tokamak (EAST) has proven to be an effective method reduce fuel recycling and control impurity level, also improve plasma performance. In 2014, upper graphite divertor EAST was upgraded into a full tungsten (W) one with ITER-like actively water-cooled monoblock structure. Note that there is still large surface area first covered by tiles, including lower divertor, NBI shine through armor,...
A laser based method combined with spectroscopy, such as laser-induced breakdown spectroscopy (LIBS) and ablation (LIAS), is a promising technology for plasma-wall interaction studies. In this work, we report the development of in situ laser-based diagnostics (LIBS LIAS) assessment static dynamic fuel retention on first wall without removing tiles between during plasma discharges Experimental Advanced Superconducting Tokamak (EAST). The was measured after different conditioning methods daily...
In this paper, we will experimentally investigate the power threshold (PL-H) in upper single null plasmas with an ITER-like tungsten divertor under different ∇B drift directions on EAST [F. Ding et al., Commissioning and PSI Behavior of ITER-Like W/Cu Divertor 22nd PSI, Rome (2016)]. The for low (L) to high (H) confinement mode has a clear positive toroidal magnetic field, BT, dependence when points toward primary X-point (B×∇B↑). A factor 2–3 increase PL-H is observed away from (B×∇B↓)....
A test assembly of carbon coated molybdenum tiles was exposed to a sequence well-diagnosed ohmic helium discharges in the Experimental Advanced Superconducting Tokamak (EAST) using material and plasma evaluation system. The configured approximate, on reduced scale, profile first-wall panel ITER. Net erosion deposition determined from measurements thickness surface layer by ion-beam analysis before after exposure. highest 800 nm, or about one third initial thickness, occurred near EAST...
• The deposited W layer was formed by hydrogen plasma sputtering. were exposed to EAST deuterium plasma. A release clearly observed from the Deuterium peaks close that irradiated ions at 573 K. Retained in had a peak about 50 nm layers on plate sputtering together with bare plate. In TDS measurement, addition of which incorporated during sputtering-deposition processes. On other hand, isotope not detected This suggests formation increases tritium inventory confinement vessel. Although...