A5030195680- Fusion materials and technologies
- Nuclear Materials and Properties
- Microstructure and mechanical properties
- High-Velocity Impact and Material Behavior
- Hydrogen embrittlement and corrosion behaviors in metals
- Metal and Thin Film Mechanics
- Advanced materials and composites
- Graphite, nuclear technology, radiation studies
- Nuclear reactor physics and engineering
Beihang University
2021-2024
Abstract Melt ejection and melt motion of tungsten (W) as a plasma-facing material due to accidental thermal overload events are primary concerns for ITER DEMO. Previous experiments have revealed that W-1wt.% La₂O₃ is an effective suppressing cavitation under single pulsed heat load [1]. To further investigate this effect, both W (WL10) were subjected multiple exposures in the high flux facility GLADIS tokamak ASDEX Upgrade (AUG). In GLADIS, H/He high-power neutral particle beams used, with...
Abstract Surface damage and microscopic defect evolution of tungsten (W) armor under transient heat loads are key factors for fuel retention in fusion reactors. In this work, experiments were conducted to investigate the effects cyclic thermal shocks on deuterium (D) surface blistering W. Thermal shock recrystallized W using an electron beam with a power density 0.15 GW m −2 across 100–1500 cycles, followed by D plasma exposure high-fluence (∼1 × 10 26 ). The results demonstrate that samples...
Temperature is one of the critical factors that strongly affect behavior hydrogen isotopes in tungsten (W). This work investigates effect initial exposure temperature on deuterium (D) retention and surface blistering recrystallized W. D plasma started at 420 K 600 K, respectively, then changed to same 520 K. For each temperature, irradiation fluence ∼ 1 × 1026 m−2, therefore total 2 m−2 for sample. A reference W sample was also exposed with fluence. Compared sample, it found significantly...
Abstract Understanding the behavior of tungsten (W) surface damage under synergistic effects high heat flux loading and helium (He) irradiation is essential for predicting material performance during off-normal operations in ITER. In this study, modifications occurring at temperatures (> 2200 K) up to melting point were investigated by conducting experiments involving two campaigns Vertical Displacement events (VDEs) like He neutral beam pulse on polycrystalline W samples test facility...
In ITER and future tokamaks, high heat flux loads will lead to recrystallization decrease in toughness thermal shock resistance of tungsten plasma facing materials, resulting crack network formation possible failure. this study, tests blank, helium-plasma-exposed helium-ion-irradiated rolled with/without isothermal annealing are conducted. Without annealing, cracks start form blank at the power density 0.35 GW/m2, while no observed on loaded surface ones. After 1473 K for 1 h, fractions...