Organizational Unit:

Fusion Research Center

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https://hdl.handle.net/1853/70733

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Organizational Unit

George W. Woodruff School of Mechanical Engineering

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https://finding-aids.library.gatech.edu/agents/corporate_entities/1150

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Publication Search Results

Now showing 1 - 10 of 59

A Supplemental Fusion-Fission Hybrid Path to Fusion Power Development

(Georgia Institute of Technology, 2012-07-21) Stacey, Weston M.
Sustainable Nuclear Power

(Georgia Institute of Technology, 2012-03-15) Stacey, Weston M.
Suggested DIII-D Research Focus on Pedestal/Boundary Physics

(Georgia Institute of Technology, 2012-01-26) Stacey, Weston M.
Non-Diffusive Transport in the Tokamak Edge Pedestal

(Georgia Institute of Technology, 2012) Stacey, Weston M. ; Groebner, Rich J. ; Evans, T. E.

There are (at least) two classical mechanisms for non-diffusive transport in the edge plasma: i) particle “pinch” velocities due to forces such as VxB, and Er; and ii) outward drifts due to ion-orbit loss and X-transport. A theoretical development for the treatment of these non-diffusive transport mechanisms within the context of fluid theory is assembled and applied to several DIII-D discharges in order to investigate the importance of these non-diffusive transport mechanisms in the edge pedestal. Several interesting insights emerge from this investigation.
Role of Fusion in the Sustainable Expansion of Nuclear Power

(Georgia Institute of Technology, 2011-11-29) Stacey, Weston M.
The Effect of Ion Orbit Loss and X-Loss on the Interpretation of Ion Energy and Particle Transport in the DIII-D Edge Plasma

(Georgia Institute of Technology, 2011-10-14) Stacey, Weston M.

Calculation models are presented for treating ion orbit loss effects in interpretive fluid transport calculations for the tokamak edge pedestal. Both standard ion orbit loss of particles following trapped or passing orbits across the separatrix and the X-loss of particles that are poloidally trapped in a narrow null-Bθ region extending inward from the X-point, where they gradB and curvature drift outward, are considered. Calculations are presented for a representative DIII-D [J. Luxon, Nucl. Fusion 42, 614 (2002)] shot which indicate that ion orbit loss effects are significant and should be taken into account in calculations of present and future experiments.
Tutorial: Principles and Rationale of the Fusion-Fission Hybrid Burner Reactor

(Georgia Institute of Technology, 2011-09-13) Stacey, Weston M.

The potential advantages of Fusion-Fission Hybrid (FFH) reactors (relative to critical fast reactors) for closing the back end of the nuclear fuel cycle are discussed. The choices of fission and fusion technologies for FFH burner reactors that would fission the transuranics remaining in spent fuel discharged from nuclear power reactors are summarized. The conceptual design and fuel cycle performance of the SABR FFH burner reactor are presented, and a fusion power development schedule with a symbiotic dual FFH path is outlined.
Force Balance and Ion Particle Transport Differences in High and Low Confinement Tokamak Edge Pedestals

(Georgia Institute of Technology, 2010-11-22) Stacey, Weston M. ; Groebner, Rich J.

The various terms in the radial force balance in the edge plasma are evaluated using experimental data from the low (L) and high (H) confinement phase of a DIII-D [J. Luxon, Nucl. Fusion 42, 614 (2002)] discharge in order to investigate the differences in the radial force balance among the several electromagnetic and pressure gradient forces in L-mode and H-mode. The roles of cross-field toroidal momentum transport and of a radial pinch velocity in determining different radial particle fluxes in L-mode and H-mode are elucidated
Evolution of the H-mode edge pedestal between ELMs

(Georgia Institute of Technology, 2010-08) Stacey, Weston M. ; Groebner, Rich J.

The evolution of edge pedestal parameters between edge-localized modes (ELMs) is analyzed for an H-mode DIII-D [J Luxon, Nucl. Fusion 42, 612 (2002)] discharge. Experimental data are averaged over the same sub-intervals between successive ELMs to develop data that characterize the evolution of density, temperature, rotation velocities, etc. over the interval between ELMs. These data are interpreted within the context of the constraints imposed by particle, momentum and energy balance, in particular in terms of the pinch-diffusion relation for radial particle flux that is required by momentum balance. It is found that in the edge pedestal there is an increase of both inward (pinch) electromagnetic and outward (diffusive) pressure gradient forces over the inter-ELM interval.
The effects of rotation, electric field, and recycling neutrals on determining the edge pedestal density profile

(Georgia Institute of Technology, 2010-05-19) Stacey, Weston M.

The edge density profile is calculated from the continuity and momentum balance equations, using experimental electric field and rotation velocities and a calculated recycling neutral source, to evaluate the relative importance of these quantities in determining the observed structure of the edge density profile in a DIII-D _J. Luxon, Nucl. Fusion 42, 614 _2002__ high-confinement mode discharge.