D. McColl

ORCID: 0000-0002-0614-2291
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About
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Research Areas
  • Magnetic confinement fusion research
  • Ionosphere and magnetosphere dynamics
  • Particle accelerators and beam dynamics
  • Fusion materials and technologies
  • Plasma Diagnostics and Applications
  • Superconducting Materials and Applications
  • Laser-Plasma Interactions and Diagnostics
  • Solar and Space Plasma Dynamics
  • Electromagnetic Launch and Propulsion Technology
  • Electrostatic Discharge in Electronics
  • Ion-surface interactions and analysis
  • Diamond and Carbon-based Materials Research
  • Metal and Thin Film Mechanics
  • Tunneling and Rock Mechanics
  • Spectral Theory in Mathematical Physics
  • Advanced Materials Characterization Techniques
  • Atomic and Molecular Physics
  • Hydraulic and Pneumatic Systems
  • Tribology and Lubrication Engineering
  • Nuclear Physics and Applications
  • Control Systems in Engineering
  • Microfluidic and Capillary Electrophoresis Applications
  • Physics of Superconductivity and Magnetism
  • Oceanographic and Atmospheric Processes

University of Saskatchewan
1997-2022

General Atomics (United States)
1983

University of California, Berkeley
1982

Observation of the intensity recycling particle flux at main plasma edge for various limiter and divertor discharges indicates that gross energy confinement beam-heated is closely related to flux. In discharges, global time τE show many similarities: 1) linear Ip dependence < 600 kA, 2) no BT dependence, 3) deterioration against injection power. Improvement by increasing Ip, example, associated with high temperatures region accompanied reduced recycling. – Divertor low around better than...

10.1088/0029-5515/24/2/005 article EN Nuclear Fusion 1984-02-01

Using a neutral-beam injection power of 3.4 M W, volume-averaged toroidal betas up to ⟨βT⟩ = 4.5% have been obtained in low-toroidal-field, low-qψ, vertically elongated discharges the Doublet III tokamak. This level is above minimum required for tokamak reactor, thus demonstrating that reactor values are possible device. The observed enhancement with vertical elongation lends confidence design future devices which rely on elongation.

10.1088/0029-5515/23/4/012 article EN Nuclear Fusion 1983-04-01

In compact torus injection (CTI) experiments on the STOR-M tokamak, an ion Doppler spectrometer is installed to observe effects of CTI toroidal plasma flows. The intrinsic flow in ohmic discharges without sheared with counter current core region and co-current direction at periphery. With tangential along direction, velocity decreases by more than 5 km s−1, while periphery increases 3–4 s−1. These data indicate that observed change due momentum. Density increase high soft x-ray emission...

10.1088/0741-3335/55/3/035003 article EN Plasma Physics and Controlled Fusion 2013-01-28

A new kind of quasi-coherent mode was observed in ohmic plasma the STOR-M tokamak. It is featured with a clear solitary peak around 30–35 kHz power spectra ion saturation current Langmuir probe as well poloidal and toroidal numbers (m = 1,n 0) per prediction conventional geodesic acoustic (GAM) theory. The dispersion relation also similar to GAM it shows collisional damping. In contrast GAM, floating potential ϕ GAM-like does not show symmetric 0,n 0), but has 1). pronounced magnetic...

10.1088/1741-4326/aa9a4f article EN Nuclear Fusion 2017-11-14

A compact torus (CT) injector operated at high repetition rates has been developed. system consisting of a stack insulated-gate bipolar transistors and storage capacitor banks (slow banks) for repetitive operation installed on the circuit both CT formation acceleration. Following installation silicon-controlled rectifiers purpose triggering ignitrons discharge circuits, rate 10 Hz was achieved University Saskatchewan Injector.

10.1109/tps.2015.2499218 article EN IEEE Transactions on Plasma Science 2015-12-09

One cycle alternating current (AC) plasma operation without a dwell time has been achieved in the STOR-M tokamak with good reproducibility using newly developed ohmic heating circuit. The of +24 kA is smoothly ramped down 10 ms rampdown rate around 2.0 kA/ms and then up to between -20 -24 directly time. density (3.7+or-0.6)*1018 m-3 remains at reversal as observed recent soft landing experiments. key successful, reproducible direct transition AC operations on control both total vertical...

10.1088/0029-5515/36/10/i06 article EN Nuclear Fusion 1996-10-01

Complete one cycle and 1.5 ac operations are performed in the STOR-M tokamak with plasma current of ∼20 kA using newly developed feedback control Ohmic heating circuits. Bias voltage adjustment is installed position circuit to optimize second negative phase for multicycle operation. The key successful, reproducible on both total vertical field by system application bias voltage.

10.1063/1.1148184 article EN Review of Scientific Instruments 1997-07-01

A pulsed oscillating power amplifier has been developed to apply high frequency biasing voltage an electrode at the edge of STOR-M tokamak plasma. The can deliver a peak-to-peak up 120V and current 30A within range 1kHz-50kHz. is located in equatorial plane radius $\rho = 0.88$. applied varied between discharges. It observed that plasma density soft x-ray intensity from core region usually increase lower regime 1kHz-5kHz as well relatively higher 20kHz-25kHz but seldom them. Increment...

10.1088/1741-4326/ab945c article EN Nuclear Fusion 2020-05-19

Reproducible plasma current start-up without a central solenoid (CS) has been demonstrated using the outer ohmic heating (OH) coils in iron core STOR-M tokamak (Mitarai et al 2014 Fusion Eng. Des. 89 2467–71). Although OH coil saturates eventually, it that can be maintained during saturation phase. In this work, further studies have conducted to investigate effects of turn number (N = 4 or N 6) CS-less discharges and evaluate stability with respect n-decay index vertical magnetic field. For...

10.1088/0029-5515/55/6/063034 article EN Nuclear Fusion 2015-05-22

A plasma current up to 15 kA has been driven with outer ohmic heating (OH) coils in the STOR-M iron core tokamak. Even when inner OH coil is disconnected, alone can induce as primary windings and initial breakdown are even easier this layout. This result suggests a possibility use an spherical tokamak start without central solenoid. The effect of saturation on extension discharge pulse length estimated for further experiments

10.1063/1.4915316 article EN Review of Scientific Instruments 2015-03-01

A particle simulation code has been modified to simulate loss caused by quadrupole magnetic fields on a field-reversed mirror plasma device. Since analytic are chosen for the equilibrium, numerical algorithm is highly accurate long-time integrations of orbits. The resultant due can be competitive with collisional in

10.13182/fst82-a20736 article EN Nuclear Technology - Fusion 1982-01-01

Summary form only given. Effect of atomic number operating gas on hard x-ray and ion beam emission from plasma focus have been studied. Circuit analyses done quantitatively to measure voltage inductance focusing plasma. The results show increasing the gas, increase energy generated ions, intensify radiation x-r a y, enhancing amount injected in during pinching time. Based measured it is speculated that (Z≥18) might drive condition radiation-enhanced compression pinch phase.

10.1109/plasma.2016.7533993 article EN 2020 IEEE International Conference on Plasma Science (ICOPS) 2016-06-01
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