A5031511252- Magnetic confinement fusion research
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Aerosol Filtration and Electrostatic Precipitation
- Electromagnetic Launch and Propulsion Technology
- Insects and Parasite Interactions
- Insect and Arachnid Ecology and Behavior
- Nuclear reactor physics and engineering
- Cold Fusion and Nuclear Reactions
- Plasma Diagnostics and Applications
- Particle accelerators and beam dynamics
University of Tennessee at Knoxville
2022-2024
Knoxville College
2022
Abstract High-Z plasma facing components redeposit within the sheath through a combination of two distinct mechanisms: prompt (or geometric-driven) and local sheath-driven) redeposition. Experimental efforts are needed to determine leading-order parameters influencing prompt-vs-local trade-off, which sets fraction material entering scrape-off layer. In preparation for such experiments, isolated PYEAD-RustBCA-GITR coupled net erosion code using Sobol’ sensitivity analysis. Then, experiments...
Abstract Experimental data, together with interpretive modeling tools, are examined to study trends in the tungsten (W) source all-W environment of WEST tokamak, both from divertor and main chamber. In particular, a poloidal limiter protecting an ion cyclotron resonance heating (ICRH) antenna is used as proxy for chamber sourcing. The key carried out by stepping up lower hybrid current drive (LHCD) power, only auxiliary power source. Limiter W sources exhibit qualitatively similar...
The interaction of radio frequency (RF) sheaths with fusion reactor relevant materials (e.g., tungsten and titanium diboride) is being studied on the RF Plasma Interaction Experiment (RF PIE). PIE consists an electron cyclotron resonance (ECR) plasma source (2.45 GHz, 5 kW) a biased heated electrode that used to simulate antenna surfaces in contact edge plasma. Helium plasmas (density <inline-formula xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">...
WEST is an actively cooled, long-pulse tokamak with nearly all plasma-facing components (PFC) made of tungsten. One the aims to study plasma operations tungsten PFCs in preparation for on high-Z divertor devices, such as ITER. For operation, impurity content and transport core are critical concerns that require further measurement interpretation improve performance PFC durability. This work details influxes during a series discharges which lower hybrid (LH) injected power was incrementally...
The plasma background and impurity transport in the scrape-off layer (SOL) of WEST tokamak are modeled for three discharges over a Psep power scan ranging between 1.5 2.35 MW. An extended modeling grid is used to investigate far-SOL sourcing from baffle lower divertor. Divertor Langmuir probe data at targets upstream reciprocating probes interferometry/reflectometry create simulated with OSM EIRENE codes. W-I spectroscopic divertor estimate sputtered W flux as an input code DIVIMP. A...
Accurately predicting redeposition is vital for high-Z plasma-facing component (PFC) survivability in magnetic confinement fusion. In this study, we categorize into three mechanisms: geometric-driven (prompt), sheath-driven (local), and scrape-off-layer-driven (far) redeposition. To investigate these mechanisms, employ Monte Carlo transport codes to simulate azimuthally symmetric tungsten source erosion a tokamak. By iteratively analyzing critical parameters, evaluate scaling each mechanism....