R.J. Hawryluk
A5043517847- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Fusion materials and technologies
- Plasma Diagnostics and Applications
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Ionosphere and magnetosphere dynamics
- Atomic and Molecular Physics
- Semiconductor materials and devices
- Nuclear reactor physics and engineering
- Laser-induced spectroscopy and plasma
- Electron and X-Ray Spectroscopy Techniques
- Diamond and Carbon-based Materials Research
- Metal and Thin Film Mechanics
- Dust and Plasma Wave Phenomena
- Cold Fusion and Nuclear Reactions
- Advancements in Photolithography Techniques
- Atomic and Subatomic Physics Research
- Solar and Space Plasma Dynamics
- Scientific Measurement and Uncertainty Evaluation
- Nuclear Physics and Applications
- Electromagnetic Launch and Propulsion Technology
- Mass Spectrometry Techniques and Applications
- Plasma Applications and Diagnostics
- Advanced Data Storage Technologies
Princeton Plasma Physics Laboratory
2003-2021
Max Planck Institute for Plasma Physics
2019
Ludwig-Maximilians-Universität München
2019
Princeton University
1995-2009
Oak Ridge National Laboratory
1978-2007
Massachusetts Institute of Technology
1972-1997
Los Alamos National Laboratory
1990-1997
General Atomics (United States)
1997
University of Wisconsin–Madison
1986-1997
Columbia University
1991-1997
Strong magnetohydrodynamic activity has been observed in PDX neutral-beam-heated discharges. It occurs for ${\ensuremath{\beta}}_{T}q>~0.045$ and is associated with a significant loss of fast ions drop neutron emission. As much as 20%-40% the beam heating power may be lost. The instability repetitive bursts oscillations \ensuremath{\le} 1 msec duration at 1-6-msec intervals. dubbed "fishbone instability" from its characteristic signature on Mirnov coils.
Neutral-beam heating of plasmas in the Tokamak Fusion Test Reactor at low preinjection densities [${n}_{e}$(0)\ensuremath{\simeq}${10}^{19}$ ${\mathrm{m}}^{\mathrm{\ensuremath{-}}3}$] were characterized by ${T}_{e}$(0)=6.5 keV, ${T}_{i}$(0)=20 ${n}_{e}$(0)=7\ifmmode\times\else\texttimes\fi{}${10}^{19}$ ${\mathrm{m}}^{\mathrm{\ensuremath{-}}3}$, ${\ensuremath{\tau}}_{E}$=170 msec, ${\ensuremath{\beta}}_{\mathrm{theta}}$=2, and a d(d,n${)}^{3}$He neutron emission rate ${10}^{16}$...
As part of the ITER Design Review and in response to issues identified by Science Technology Advisory Committee, physics requirements were reviewed as appropriate updated. The focus this paper will be on recent work affecting design with special emphasis topics near-term procurement arrangements. This describe results on: sensitivity studies, poloidal field coil requirements, vertical stability, effect toroidal ripple thermal confinement, material choice heat load for plasma-facing...
Neutral-beam--heated plasmas in TFTR show evidence of substantial non-Ohmically driven toroidal current, even for balanced beam momentum input. The observations are inconsistent with calculations including only Ohmic and beam-driven currents, presently can be matched by models the neoclassical bootstrap current.
Monte Carlo calculations have been performed to determine the spatial distribution of energy dissipated in a 4000-Å-thick film polymethyl methacrylate (PMMA), due an incident electron beam. The were for 5-, 10-, and 20-keV electrons on silicon substrate also copper gold substrates. effect varying beam diameter from 250 3000 Å was evaluated. A detailed comparison is made between results analytic models used predict dissipated. plural scattering model found be good agreement with calculations,...
Peak fusion power production of 6.2\ifmmode\pm\else\textpm\fi{}0.4 MW has been achieved in TFTR plasmas heated by deuterium and tritium neutral beams at a total 29.5 MW. These have an inferred central alpha particle density 1.2\ifmmode\times\else\texttimes\fi{}${10}^{17}$ ${\mathrm{m}}^{\mathrm{\ensuremath{-}}3}$ without the appearance either disruptive magnetohydrodynamics events or detectable changes Alfv\'en wave activity. The measured loss rate energetic particles agreed with...
Experimental results from high-power neutral-beam-injection experiments on the Princeton Large Torus tokamak are reported. At highest beam powers (2.4 MW) and lowest plasma densities [${n}_{e}(0)=5\ifmmode\times\else\texttimes\fi{}{10}^{13}$ ${\mathrm{cm}}^{\ensuremath{-}3}$], ion temperatures of 6.5 keV achieved. The collisionality ${{\ensuremath{\nu}}_{i}}^{*}$ drops below 0.1 over much radial profile. Electron heating $\frac{\ensuremath{\Delta}{T}_{e}}{{T}_{e}}\ensuremath{\approx}50%$ has...
A potentially attractive next-step towards fusion commercialization is a pilot plant, i.e. device ultimately capable of small net electricity production in as compact facility possible and configuration scalable to full-size power plant. key capability for pilot-plant programme the high neutron fluence enabling nuclear science technology (FNST) research. It found that physics assumptions between those assumed ITER nth-of-a-kind it provide FNST-relevant wall loading devices. Thus, may be...
Recent scientific and technical progress in magnetic fusion experiments has resulted the achievement of plasma parameters (density temperature) which made possible production significant bursts power from deuterium-tritium fuels first studies physics burning plasmas. The key issues studying reacting core are confinement, magnetohydrodynamic (MHD) stability, confinement loss energetic products fuel ions. Progress development regimes operation that both have good MHD stable a broad study...
After many years of fusion research, the conditions needed for a D–T reactor have been approached on Tokamak Fusion Test Reactor (TFTR) [Fusion Technol. 21, 1324 (1992)]. For first time unique phenomena present in plasma are now being studied laboratory plasma. The magnetic experiments to study plasmas using nearly equal concentrations deuterium and tritium carried out TFTR. At maximum power 10.7 MW, 39.5 MW neutral-beam heating, supershot discharge 6.7 high-βp following current rampdown....
Low-Z impurity transport in tokamaks was simulated with a one-dimensional model including both neoclassical and anomalous transports. The fluxes are due to collisions between the background plasma ions as well various ionization states. evaluation of takes into account different collisionality regimes ions. A limiter scrape-off is used define boundary condition for periphery. To spectroscopic measurements power radiated by lower states, included. sensitivities results uncertainties rate...
Fusion neutron emission of 1.5 × 1014 neutrons · s−1 and 2 1013 neutrons/pulse has been observed for PLT deuterium discharges with up to 2.5 MW neutral-beam injection. The time evolution magnitude are consistent theoretical calculations the fusion reactions caused by energetic injected ions which confined slow down classically. factor-of-two accuracy in absolute calibration is major uncertainty comparison theory. Neutron sawtooth oscillations (⪅ 3%) can also be explained
Tokamaks are sensitive to deviations from axisymmetry as small δB/B0∼10−4. These nonaxisymmetric perturbations greatly modify plasma confinement and performance by either destroying magnetic surfaces with subsequent locking or deforming associated nonambipolar transport. The Ideal Perturbed Equilibrium Code (IPEC) calculates ideal perturbed equilibria provides important basis for understanding the sensitivity of tokamak plasmas perturbations. IPEC calculations indicate that response,...
The Tokamak Fusion Test Reactor (TFTR) (R. J. Hawryluk, to be published in Rev. Mod. Phys.) experiments on high-temperature plasmas, that culminated the study of deuterium–tritium D–T plasmas containing significant populations energetic alpha particles, spanned over two decades from conception completion. During design TFTR, key physics issues were magnetohydrodynamic (MHD) equilibrium and stability, plasma energy transport, impurity effects, reactivity. Energetic particle was given less...
The Tomamak Fusion Test reactor has performed initial high-power experiments with the plasma fueled nominally equal densities of deuterium and tritium. Compared to pure plasmas, energy stored in electron ions increased by \ensuremath{\sim}20%. These increases indicate improvements confinement associated use tritium possibly heating electrons \ensuremath{\alpha} particles created D-T fusion reactions.
The poloidal field (PF) coil system on ITER, which provides both feedforward and feedback control of plasma position, shape, current, is a critical element for achieving mission performance. Analysis PF capabilities has focused the 15 MA Q = 10 scenario with 300–500 s flattop burn phase. operating space available ELMy H-mode discharges in ITER upgrades to coils or associated systems establish confidence that objectives can be reached have been identified. Time dependent self-consistent...
Recent operation of the Tokamak Fusion Test Reactor (TFTR) [Plasma Phys. Controlled Nucl. Research 1, 51 (1986)] has produced plasma equilibria with values Λ≡βp eq+li/2 as large 7, εβp dia≡2μ0ε〈p⊥〉/〈〈Bp〉〉2 1.6, and Troyon normalized diamagnetic beta 26, 209 (1984); Lett. 110A, 29 (1985)], βNdia≡108〈βt⊥〉aB0/Ip 4.7. When dia≳1.25, a separatrix entered vacuum chamber, producing naturally diverted discharge that was sustained for many energy confinement times, τE. The largest stored were...
A review of TFTR plasma transport studies is presented. Parallel and the confinement suprathermal ions are found to be relatively well described by theory. Cross-field thermal plasma, however, anomalous with momentum diffusivity being comparable ion larger than electron in neutral beam heated discharges. Perturbative experiments have studied nonlinear dependencies coefficients examined role possible nonlocal phenomena. The underlying turbulence has been using microwave scattering, emission...
Circular-limiter H modes are obtained on the TFTR tokamak during high-power neutral-beam heating. The transition is usually from supershot to mode rather than usual L transition, and thus in a low-recycling environment with core fueling mainly heating beams. As result, density pressure profiles highly peaked at center. global confinement time ${\mathrm{\ensuremath{\tau}}}_{\mathit{E}}$ enhanced over L-mode scaling by up \ensuremath{\approxeq}2.5 times. onset of edge-localized MHD shortly...
The TFTR tokamak has reached its original machine design specifications (Ip=2.5 MA and BT=5.2 T). Recently, the D degrees neutral beam heating power been increased to 6.3 MW. By operating at low plasma current (Ip approximately=0.8 MA) density (ne approximately=1*1019 m-3), high ion temperatures (9+or-2 keV) rotation speeds (7*105 m/s) have achieved during injection. At opposite extreme, pellet injection into plasmas used increase line-average 8*1019 m-3 central 1.6*1020 m-3. This wide range...