Michael Jaworski
A5091581808- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Plasma Diagnostics and Applications
- Particle accelerators and beam dynamics
- Nuclear Materials and Properties
- Laser-Plasma Interactions and Diagnostics
- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Ionosphere and magnetosphere dynamics
- Pulsed Power Technology Applications
- Particle Accelerators and Free-Electron Lasers
- Advanced Battery Technologies Research
- Electron and X-Ray Spectroscopy Techniques
- Laser-induced spectroscopy and plasma
- Ion-surface interactions and analysis
- Dust and Plasma Wave Phenomena
- Silicon and Solar Cell Technologies
- Vacuum and Plasma Arcs
- X-ray Spectroscopy and Fluorescence Analysis
- Metal and Thin Film Mechanics
- Aerosol Filtration and Electrostatic Precipitation
- Particle Detector Development and Performance
- Energy Harvesting in Wireless Networks
- Electrostatic Discharge in Electronics
Los Alamos National Laboratory
2019-2025
Universidad Nacional de La Plata
2023
Consejo Nacional de Investigaciones Científicas y Técnicas
2023
Comisión de Investigaciones Científicas
2023
Princeton Plasma Physics Laboratory
2010-2019
Princeton University
2014-2016
University of Illinois Urbana-Champaign
2004-2010
Abstract Lithium wall coatings have been shown to reduce recycling, suppress edge-localized modes (ELMs), and improve energy confinement in the National Spherical Torus Experiment (NSTX). Here we document effect of gradually increasing lithium on discharge characteristics, with reference ELMy discharges obtained boronized, i.e. non-lithiated conditions. We observed a continuous but not quite monotonic reduction recycling improvement confinement, gradual alteration edge plasma profiles,...
Liquid metal plasma-facing components (PFCs) have been proposed as a means of solving several problems facing the creation economically viable fusion power reactors. To date, few demonstrations exist this approach in diverted tokamak and we here provide an overview such work on National Spherical Torus Experiment (NSTX). The Lithium Divertor (LLD) was installed operated for 2010 run campaign using evaporated coatings filling method. LLD consisted copper-backed structure with porous...
The Experimental Advanced Superconducting Tokamak (EAST) has demonstrated, for the first time, long-pulse divertor plasmas over 400 s, entirely driven by lower hybrid current drive (LHCD), and further extended high-confinement plasmas, i.e. H-modes, 30 s with predominantly LHCD advanced lithium wall conditioning. Many new exciting physics results have been obtained in quest operations. key findings are as follows: (1) access to H-modes EAST favours configuration ion ∇B drift directed away...
A significant fraction of high-harmonic fast-wave (HHFW) power applied to NSTX can be lost the scrape-off layer (SOL) and deposited in bright hot spirals on divertor rather than core plasma. We show that HHFW flows these along magnetic field lines passing through SOL front antenna, implying couples across entire width mostly at antenna face. This result will help guide future efforts understand minimize edge losses order maximize heating current drive.
Research on the National Spherical Torus Experiment, NSTX, targets physics understanding needed for extrapolation to a steady-state ST Fusion Nuclear Science Facility, pilot plant, or DEMO. The unique operational space is leveraged test theories next-step tokamak operation, including ITER. Present research also examines implications coming device upgrade, NSTX-U. An energy confinement time, τE, scaling unified varied wall conditions exhibits strong improvement of BTτE with decreased electron...
The National Spherical Torus Experiment (NSTX) has undergone a major upgrade, and the NSTX Upgrade (NSTX-U) Project was completed in summer of 2015.NSTX-U first plasma subsequently achieved, diagnostic control systems have been commissioned, H-mode accessed, magnetic error fields identified mitigated, physics research campaign carried out.During ten run weeks operation, NSTX-U surpassed record pulse-durations toroidal (TF), high-performance ~1 MA plasmas comparable to best sustained near...
The mission of the National Spherical Torus Experiment (NSTX) is demonstration physics basis required to extrapolate next steps for spherical torus (ST), such as a plasma facing component test facility (NHTX) or an ST based (ST-CTF), and support ITER. Key issues are transport, steady state high β operation. To better understand electron new high- k scattering diagnostic was used extensively investigate gyro-scale fluctuations with varying temperature gradient scale length. Results from n = 3...
Fast-wave heating and current drive efficiencies can be reduced by a number of processes in the vicinity antenna scrape-off layer (SOL). On NSTX from around 25% to more than 60% high-harmonic fast-wave power lost SOL regions, large part this flows along magnetic field lines is deposited bright spirals on divertor floor ceiling. We show that field-line mapping matches location heat deposition lower divertor, albeit with portion outside predictions. The then used partially reconstruct profile...
Developing a reactor-compatible divertor has been identified as particularly challenging technology problem for magnetic confinement fusion. Application of lithium (Li) in NSTX resulted improved H-mode confinement, power threshold reduction, and other plasma performance benefits. During the 2010 campaign, application relatively modest amount Li (300 mg prior to discharge) ∼50% reduction heat load on liquid (LLD) attributable enhanced bolometric radiation. These promising results related...
To develop realistic liquid lithium divertors for future fusion reactors, this paper aims to improve the understanding of their power handling capabilities. A divertor target prototype, designed facilitate metal experiments in tokamaks, was tested Magnum-PSI. The has an internal reservoir pre-filled with and passively re-supply textured plasma facing surface during operation. assess capability exposed helium plasmas increasing flux density linear device temperature response targets recorded...
Liquid metal plasma-facing components (PFCs) have been proposed as a means of solving several problems facing the creation economically viable fusion power reactors. metals face critical issues in three key areas: free-surface stability, material migration and demonstration integrated scenarios. To date, few demonstrations exist this approach diverted tokamak we here provide an overview such work on National Spherical Torus Experiment (NSTX). The liquid lithium divertor (LLD) was installed...
Abstract Lithium-coated high- Z substrates are planned for use in the NSTX-U divertor and a candidate plasma facing component (PFC) reactors, but it remains necessary to characterize gross Li erosion rate under high fluxes (>10 23 m −2 s −1 ), typical region. In this work, realistic model compositional evolution of Li/D layer is developed that incorporates first principles molecular dynamics (MD) simulations D diffusion liquid Li. Predictions from mixed material also include formation...
The National Spherical Torus Experiment Upgrade (NSTX-U) will advance the physics basis required for achieving steady-state, high-beta, and high-confinement conditions in a tokamak by accessing high toroidal fields (1 T) plasma currents (1.0–2.0 MA) low aspect ratio geometry (A = 1.6–1.8) with flexible auxiliary heating systems (12 MW NBI, 6 HHFW). This paper describes progress development of L- H-mode discharge scenarios commissioning operational tools first ten weeks operation that enable...
A high density Langmuir probe array has been developed for measurements of scrape-off layer parameters in NSTX. Relevant scale lengths heat and particle fluxes are 1-5 cm. Transient edge plasma events can occur on a time several milliseconds, the duration typical discharge is ∼1 s. The consists 99 individual electrodes arranged three parallel radial rows to allow both swept triple-probe operation mounted carbon tile located lower outer divertor NSTX between two segments newly installed...