A5029097407- Fusion materials and technologies
- Nuclear Materials and Properties
- Ion-surface interactions and analysis
- Magnetic confinement fusion research
- Laser-induced spectroscopy and plasma
- Laser-Plasma Interactions and Diagnostics
- Metal and Thin Film Mechanics
- Plasma Diagnostics and Applications
- Metallurgical Processes and Thermodynamics
- Nuclear reactor physics and engineering
- Advancements in Photolithography Techniques
- Electron and X-Ray Spectroscopy Techniques
- Diamond and Carbon-based Materials Research
- Laser Material Processing Techniques
- High-Temperature Coating Behaviors
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Semiconductor materials and devices
- Integrated Circuits and Semiconductor Failure Analysis
- Nuclear Physics and Applications
- X-ray Spectroscopy and Fluorescence Analysis
- Laser Design and Applications
- Atomic and Molecular Physics
- Advanced Materials Characterization Techniques
- Electrohydrodynamics and Fluid Dynamics
Purdue University West Lafayette
2015-2024
National Research Centre
2023
Assiut University
1970-2023
Concordia University
2023
Al-Azhar University
2009-2020
Egyptian Atomic Energy Authority
2018
Purdue University System
2013-2014
Cornell University
2013
Samsung (South Korea)
2013
V. N. Karazin Kharkiv National University
2010
A new "nanopumping" effect consisting of the activation an axial gas flow inside a carbon nanotube by producing Rayleigh traveling waves on surface is predicted. The driving force for friction between particles and walls. molecular dynamics simulation was carried out showing macroscopic flows atomic hydrogen helium gases in nanotube.
Tungsten is the leading high-Z candidate surface material for magnetic fusion reactor plasma-facing components, however, there are specific performance concerns tungsten, and a general major concern about relying on one material. To broaden options development we identified examined five potential alternative materials: zirconium, niobium, molybdenum, hafnium tantalum. We assess these materials from three standpoints: neutron-induced activation, sputter erosion/redeposition plasma transient...
Tungsten has been chosen as the main candidate for plasma facing components (PFCs) due to its superior properties under extreme operating conditions in future nuclear fusion reactors such ITER. One of serious issues PFCs is high heat load during transient events ELMs and disruption reactor. Recrystallization grain size growth PFC materials caused by transients are undesirable changes material, since isotropic microstructure developed after recrystallization exhibits a higher...
We assess key plasma–surface interaction issues of an all-metal plasma facing component (PFC) system for ITER, in particular a tungsten divertor, and beryllium or first wall. Such eliminates problems with carbon divertor erosion T/C codeposition, all-tungsten would better extrapolate to post-ITER devices. The studied are sputtering, transport formation mixed surface layers, tritium contamination, edge-localized mode (ELM) response He-on-W irradiation effects. Code package OMEGA computes PFC...
Plasma-facing components (PFCs) in tokamaks are exposed to high-heat loads during abnormal events such as plasma disruptions and edge-localized modes. The most significant erosion contamination problem is macroscopic melt splashes losses from metallic divertor plates wall materials into core plasma. classical linear stability analysis used assess the initial conditions for development growth of surface waves at plasma–liquid metal interface. maximum velocity difference critical wavelengths...
The damage and erosion of plasma-facing components (PFCs) due to extremely high heat loads particle bombardment is a key issue for the nuclear fusion community. Currently current ion electron beams are used in laboratories simulating behaviour PFC materials under ITER-like conditions. Our results indicate that high-power nanosecond lasers can be laboratory simulation flux material degradation. We exposed tungsten (W) surfaces with repetitive laser pulses from power density ~ few GW cm−2....
We investigated the effect of edge-localized mode like transient heat events on pristine samples for two different grades deformed tungsten with ultrafine and nanocrystalline grains as potential candidates plasma-facing components. Pulses from a laser beam durations ∼1 ms operating in near infrared wavelength were used simulating loading fusion devices. specifically focused investigating analysis mechanisms material removal sample surface under repetitive loads. Several techniques applied...
We investigated the expansion features of femtosecond laser generated tungsten nanoparticle plumes in vacuum. Fast gated images showed distinct two components features, viz., plasma and plumes, separated by time appearance. The persistence are ∼500 ns ∼100 μs, respectively, propagating with velocities differed 25 times. estimated temperature nanoparticles a decreasing trend increasing space. Compared to low-Z materials (e.g., Si), ultrafast ablation high-Z like W provides significantly...
Abstract The goal of this work is to assess Ta as a potential plasma-facing material for future fusion reactors in terms its response high-flux, low-energy He + ion irradiation. samples were irradiated with 100 eV ions at various fluences up 3.5 × 10 25 m −2 while simultaneously heated constant temperatures the range 823–1223 K. SEM studies show that surfaces undergo significant morphology changes have strong dependence on both fluence and sample temperature. Optical reflectivity complements...