A5021579793- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Nuclear Materials and Properties
- Nuclear Physics and Applications
- Metal and Thin Film Mechanics
- Diamond and Carbon-based Materials Research
- Semiconductor materials and devices
- Spacecraft and Cryogenic Technologies
- Plasma Diagnostics and Applications
- Particle Accelerators and Free-Electron Lasers
Korea Institute of Fusion Energy
2011-2021
A new infra-red (IR) thermography system with high spatial resolution has been installed on KSTAR and is now mainly applied to measure the outer divertor heat load profile. The first measurement results of profiles between ELMs have characterize inter-ELMs loads in H-mode plasmas. In particular, power decay length (λq) profile determined by fitting a convolution an exponential Gaussian function. analysis shows good agreement recent multi-machine λq scaling, which predicts be ∼1 mm under...
Massive gas injection (MGI) system was developed on Korea Superconducting Tokamak Advanced Research (KSTAR) in 2011 campaign for disruption studies. The MGI valve has a volume of 80 ml and maximum pressure 50 bar, the diameter orifice to vacuum vessel is 18.4 mm, distance between plasma edge ~3.4 m. power supply employs large capacitor 1 mF with voltage 3 kV, can be opened less than 0.1 ms, amount controlled by imposed voltage. During KSTAR campaign, disruptions are carried out triggering...
A series of leading edge heat load experiments are performed in KSTAR to study power balance and support a divertor shaping decision on ITER. Tungsten blocks with edges various heights were fabricated, adjusted mounted central extreme care avoid the intrinsic misalignment caused by engineering limits. The results from IR measurements COMSOL simulation consistent each other discrepancy found at JET does not exist KSTAR. simple calculation geometrical projection can be used foreseen arbitrary...
The Korea Superconducting Tokamak Advanced Research (KSTAR) device, constructed in 2008, is a world-class superconducting tokamak fusion research device for the development of energy. expected heating power goal has been set to 12 MW by using an additional system, i.e., second neutral beam injection (NBI) system NBI-2. As increases, resistance high heat flux and cooling capacity at divertor should be improved exhaust scrape-off-layer domain. Therefore, upgrade KSTAR was launched 2019, will...
Abstract When PFCs have castellated structure, co-deposition of fuel inside gaps between blocks is an important issue. Four different shapes tungsten were fabricated to study corresponding issues in KSTAR: Conventional “basic” rectangular shape, single chamfer leading edge, double-chamfer and rounded with two poloidal gap distances 0.5 mm 1.0 mm. These exposed plasma L- H-mode discharges during a whole campaign 2014. The taken out from the vacuum vessel after campaign. Gap deposition was...