A5100760767- Magnetic confinement fusion research
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Nuclear Physics and Applications
- Connective tissue disorders research
- Natural Language Processing Techniques
- Geomagnetism and Paleomagnetism Studies
- Laser-induced spectroscopy and plasma
- Nuclear reactor physics and engineering
- Physics of Superconductivity and Magnetism
- Bone and Dental Protein Studies
- Particle Accelerators and Free-Electron Lasers
- Tunneling and Rock Mechanics
- Characterization and Applications of Magnetic Nanoparticles
- Manufacturing Process and Optimization
- Advanced Measurement and Metrology Techniques
- Atomic and Subatomic Physics Research
- Powder Metallurgy Techniques and Materials
- Solar and Space Plasma Dynamics
- Ion-surface interactions and analysis
- High-pressure geophysics and materials
Tri Alpha Energy (United States)
2018-2025
Royal Military Academy
2020
University of Washington
2005-2016
American Institute of Aeronautics and Astronautics
2010-2016
Mitchell Institute
2009
University of Washington Applied Physics Laboratory
2007-2008
Seattle University
2005
Washington University in St. Louis
2004
Energetics (United States)
1999-2003
Joint European Torus
1992-2000
The scaling of the energy confinement in H mode plasmas with different hydrogenic isotopes (hydrogen, deuterium, DT and tritium) is investigated JET. For ELM-free modes thermal time τth found to decrease weakly isotope mass (τth ∼M-0.25±0.22), whilst ELMy shows practically no dependence ∼M0.03±0.1). Detailed local transport analysis reveals that edge region increases strongly mass, whereas core decreases (τthcore ∝ M-0.16), approximate agreement theoretical models gyro-Bohm type (τgB ∼M-0.2).
The experimental characteristics of divertor detachment in the JET tokamak with Mark I pumped are presented for ohmic, L mode and ELMy H experiments main emphasis on discharges deuterium fuelling only. range over which is observed various regimes, as well influence configuration, direction toroidal field, target material active pumping detachment, will be described. characteristics, such existence a considerable electron pressure drop along field lines scrape-off layer (SOL), compatibility...
Results are presented from a series of dedicated experiments carried out on JET in tritium, DT, deuterium and hydrogen plasmas to determine the dependence H mode power threshold plasma isotopic mass. The Pthr ∝ Aeff-1 scaling is established over whole range. This result makes it possible for fusion reactor with 50:50 DT mixture access regime about 20% less than that needed DD mixture. first systematic measurements necessary transition type I ELM regime, which occurs after mode, also...
TAE Technologies' research is devoted to producing high temperature, stable, long-lived field-reversed configuration (FRC) plasmas by neutral-beam injection (NBI) and edge biasing/control. The newly constructed C-2W experimental device (also called 'Norman') the world's largest compact-toroid (CT) device, which has several key upgrades from preceding C-2U such as higher input power longer pulse duration of NBI system well installation inner divertors with upgraded electrode biasing systems....
TAE Technologies, Inc. (TAE) is pursuing an alternative approach to magnetically confined fusion, which relies on field-reversed configuration (FRC) plasmas composed of mostly energetic and well-confined particles by means a state-of-the-art tunable energy neutral-beam (NB) injector system. TAE's current experimental device, C-2W (also called 'Norman'), the world's largest compact-toroid device has made significant progress in FRC performance, producing record breaking, high temperature...
Evidence for volume recombination in the JET divertor has been obtained from population ratios of excited states neutral hydrogen. The ratio Balmer series lines Dγ/Dα used to identify at both inner and outer target. At target onset is well correlated with plasma detachment as observed Langmuir probes While Te probe characteristics falls ∼2 eV, distribution 0.8±0.1 eV. peak density viewing across leg just above exceeds 2.5 × 1020 m-3. When becomes partially detached target, radial shows a...
The first successful results on the transfer of a coaxial helicity injection (CHI) produced discharge to inductive operation are reported. CHI-assisted plasma startup is more robust than only operation. After hand off for operation, initial 90 kA CHI-produced current drops 40 kA, then ramps up 170 using 30 mV s, 30% higher that by induction alone. These significant performance enhancing were obtained HIT-II spherical torus experiment (major/minor radius 0.3/0.2 m).
A spheromak is formed for the first time using a new steady state inductive helicity injection method. Using two injectors with odd symmetry and oscillating at 5.8 kHz, even sustained through nonlinear relaxation. about 13 kA of toroidal current 3 MW power. This much lower power threshold production than required electrode-based injection. Internal magnetic probe data, including oscillations driven by injectors, agree plasma being in Taylor state. The agreement remarkable considering only...
Abstract A mechanism for steady inductive helicity injection (SIHI) current drive has been discovered where the driving fluctuations are not generated by plasma but rather imposed injectors. Sheared flow of electron fluid distorts to current. The model accurately predicts time dependent toroidal current, injector impedance scaling, and profile produced in HIT-SI experiment. These results show that a stable equilibrium can be efficiently sustained with can, principle, controlled. Both large...
The Helicity Injected Torus [HIT-II: T. Jarboe et al., Phys. Plasmas 5, 1807 (1998)] is a low-aspect-ratio tokamak capable of both inductive (ohmic) and Coaxial Injection (CHI) current drive. HIT-II modest in size (major radius R=0.3 m, minor a=0.2 on-axis toroidal field up to 0.5 T), but has demonstrated 200 kA plasma current, using either CHI or induction separately. loop voltage, boundary flux, equilibrium are controlled by real-time flux feedback system. ohmic plasmas exhibit...
Because of its large size, single null divertor and flexible magnetic geometry, JET is capable producing the most reactor relevant plasmas any present generation tokamak. In recent DT experiments, fusion performance these was tested for first time. Over 4 MW power produced in a high power, steady state pulse 5 s, limited by duration heating power. The QE, defined simply as energy divided input over this s interval, 0.18. These ELMy H mode discharges performed up to expectations based on DD...
ADVERTISEMENT RETURN TO ISSUEPREVArticleNEXTBroad-line nuclear magnetic resonance studies of chloroperoxidaseGary E. Krejcarek, Robert G. Bryant, R. J. Smith, and Lowell P. HagerCite this: Biochemistry 1976, 15, 12, 2508–2511Publication Date (Print):June 1976Publication History Published online1 May 2002Published inissue 15 June 1976https://pubs.acs.org/doi/10.1021/bi00657a002https://doi.org/10.1021/bi00657a002research-articleACS PublicationsRequest reuse permissionsArticle...
Recent coaxial helicity injection (CHI) studies using the Helicity Injected Torus device [Redd et al., Phys. Plasmas 9, 2006 (2002)] have produced discharges with measured toroidal plasma currents up to 350kA and direct evidence of both poloidal flux amplification current buildup, resulting from a steady process on millisecond time scales. Internal magnetic probes directly measure amplification, also strong paramagnetism. Equilibrium reconstructions these discharges, only surface magnetics,...
The first sustainment of toroidal plasma current 50 kA at up to 3 times the injected currents, added in quadrature, using steady inductive helicity injection is described. Separatrix currents-currents not linking injectors-are sustained 40 kA. Decreases n=1 mode poloidal magnetic field higher amplifications indicate more quiescent, direct drive. Results are achieved HIT-SI (with a spheromak major radius 0.3 m) during deuterium operations immediately after helium operation. These results...
Experimental results on the transfer of a coaxial-helicity-injection (CHI) produced discharge to inductive operation are reported. CHI assisted plasma startup is more robust than only and reduces volt-seconds consumption. After handoff operation, initial 100 kA current drops 50 kA, then ramps up 180 using 30 mVs, about 40% higher that by induction alone. Results show initiation discharges at lower densities produce levels coupling current. Coupling from precharged central solenoid has record...
Differences in hybridization platforms used gene array analysis experiments can lead to significant differences results. In this study we quantitative reverse transcription-polymerase chain reaction (qRT-PCR) investigate discrepant results between the National Institute of Environmental Health Sciences cDNA and Affymetrix oligo evaluate hepatic expression changes rats exposed methapyrilene. Caldesmon platform showed decreases levels for high-dose methapyrilene 7-day pooled samples compared...
Experimental results on the transfer of a coaxial-helicity-injection (CHI) produced discharge to inductive operation are reported. By self-consistently increasing both injector flux and externally toroidal flux, useful CHI closed current has been increased 100 kA, which is retained during ramp. started plasmas outperform inductive-only discharges consume less volt-seconds. These significant were obtained helicity injected torus-II (Jarboe T.R. 1989 Fusion Technol. 15 7) spherical torus...
New understanding and improved parameters have been achieved on the Helicity Injected Torus with Steady Inductive helicity injection current drive (HIT-SI) experiment. The experiment has a bowtie-shaped spheromak confinement region two injectors. inductive injectors are 180° segments of small, oval cross section toroidal pinch. Spheromaks currents up to 38 kA amplification 2 only 6 MW injector power. Taylor-state model is shown agree HIT-SI surface internal magnetic profile measurements....
The Helicity Injected Torus programme has made progress in understanding relaxation and helicity injection current drive. conserving MHD activity during the inductive (ohmic) ramp demonstrates profile flattening needed for coaxial (CHI). Results from cathode anode central column CHI pulses are consistent with electron locking model of drive a pure n = 1 mode. Finally, low density CHI, compatible ohmic operation, been achieved. Some enhancement discharges application heating is shown.