A5015509101- Fusion materials and technologies
- Magnetic confinement fusion research
- Nuclear Materials and Properties
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Metallurgical Processes and Thermodynamics
- Microstructure and Mechanical Properties of Steels
- Particle accelerators and beam dynamics
Korea Institute of Fusion Energy
2015-2024
One of the main missions KSTAR is to develop long-pulse operation capability relevant production fusion energy. After a full metal wall configuration was decided for ITER, major upgrade planned, tungsten first similar JET ITER-like (coatings and bulk plasma-facing components). To accomplish upgrade, bonding technology has been developed tested. Since leading edges each castellation structure have be protected, shaping blocks studied by ANSYS simulation, miniaturized exposed Ohmic plasma...
Development of tungsten brazing technology for the upgraded Korea superconducting tokamak advanced research divertor was launched in early 2013. ITER grade block brazed on CuCrZr alloy vacuum at 980 °C 30 min using silver free alloy. An OFHC-copper used as an interlayer between and CuCuZr. The is a 0.05 mm thickness plate which component Ni–Cu–Mn. It found that optimal loading mock-up about 20 kPa. Ultrasonic test shear strength were carried out to check substrate material. And joint...
Development of tungsten brazing technology for the upgraded KSTAR divertor was launched in early 2013. ITER grade block brazed on CuCrZr alloy vacuum at 980 °C 30 minutes using silver free alloy. A OFHC-copper used as an interlayer between and CuCuZr. The is a 0.05 mm thickness plate which component Ni-Cu-Mn. It found that optimal surface roughness about 6 µm Rs loading mock-up 20 kPa. Ultrasonic test, shear strength tensile bend test were carried out to check substrate material. And joint...
Tungsten (W) monoblock that consists of W according to ITER specifications, oxygen-free high conductive copper (Cu-OFHC), and CuCrZr has been designed in preparation for KSTAR upgrade steady-state long-pulse operation with 27.5-MW heating power. Finite-element analysis performed by ANSYS Workbench. The hydraulic thermomechanical is investigate the optimal design parameters expected fatigue lifetime under operating conditions 5.4-MW/ <inline-formula...
For KSTAR divertor, tungsten (W) monoblock has been considered as plasma facing components. W components consist of three parts; pure the material, oxygen-free high conductive copper (Cu-OFHC) interlayer and CuCrZr alloy tube. Finite element analysis (FEA) is performed by using ANSYS WORKBENCH. In this paper, hydraulic thermo-mechanical to investigate optimal design parameters expected fatigue lifetime under operating conditions in KSTAR. The parameters, such armour thickness, side thickness...
The central solenoid (CS) magnet system of the KSTAR consists four pairs superconducting coils which are stacked with up-down symmetry and supporting structures can give pre-compression in a vertical direction on coil stack to sustain contact between coils. CS was mechanically preloaded about 7.3 MN at room temperature by preloading structure order preserve structural stability from thermal electromagnetic loads make misaligned. It has been shown that stably operated terms mechanical...