Liangwen Qi , Shuai Liu , Xiaodong Wen , Manqiang Du , Delong Guo , Chenxi Ren
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引用次数: 0
Abstract
Transient thermal load events have great effects on the service life of plasma-facing materials (PFCs) in tokamak steady-state operation. A compact-sized repetitive discharge coaxial gun plasma source is developed in order to simulate transient heat loads such as type I edge-localized modes (ELMs-I) in ITER. In this paper, the plasma characteristics of repeated coaxial gun and the damage effects of different frequencies on tungsten target are studied. At a constant initial condition (charging voltage, gas-flow), the voltage and current data reflects the discharge characteristics of the repeating plasma source. The gun produces helium plasma with an electron density of 1.6–2.0 × 1015 cm−3, an energy density of 0.2 MJ/m2, and a pulse width of 0.6 ms. The local surface heating evolution of W is clearly observed with the camera during repeated pulsed plasma exposure. By changing the discharge frequency of coaxial gun, it is found that the heat accumulation effect and thermal stress on the surface of tungsten target are intensified with the increase of shock frequency. High-frequency thermal shocks led to enhanced melting and accelerated crack propagation, with residual stresses on the target surface being released through crack formation. The simulation experiment results provide valuable insights into the interaction mechanisms between plasma and the first wall material at different frequencies in tokamaks.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.