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% The American Physical Society Electronic Contributed Abstract 
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\SubmittingMemberSurname{Dorland}
\SubmittingMemberGivenName{William}
\SubmittingMemberEmail{bdorland@zonker.ph.utexas.edu}
\SubmittingMemberAffil{Institute for Fusion Studies, The University of Texas}

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\begin{document}

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\Title{Enhanced Confinement Simulations}

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\AuthorSurname{Dorland}
\AuthorGivenName{W.}
\AuthorSurname{Kotschenreuther}
\AuthorGivenName{M.}
\AuthorSurname{Liu}
\AuthorGivenName{Q.~P.}
\AuthorSurname{Jones}
\AuthorGivenName{C.~S.}
\AuthorAffil{Institute for Fusion Studies, The University of Texas}
\AuthorSurname{Beer}
\AuthorGivenName{M.~A.}
\AuthorSurname{Hammett}
\AuthorGivenName{G.~W.}
\AuthorAffil{Princeton Plasma Physics Laboratory}

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\begin{abstract}

Most existing tokamaks routinely achieve enhanced confinement regimes.  In
turn, most enhanced confinement regimes rely (to some degree) upon sheared
{\bf E}$\times${\bf B} flows to stabilize the turbulence that otherwise
limits the confinement to L-mode [see for example, Biglari, Diamond and
Terry, Phys.~Fl.~B, {\bf 2} 1 (1990)].  Unfortunately, it is easily shown
that sheared {\bf E}$\times${\bf B} stabilization of microinstabilities
such as the ITG mode does not scale favorably with machine size.
Similarly, strong density peaking is technologically challenging at reactor
scales.  However, additional stabilization possibilities exist.  Using
nonlinear gyrofluid simulations in general geometry, we investigate and
compare various microinstability stabilization mechanisms in several
existing enhanced confinement modes.  Experimental datasets from JET,
DIII-D, C-Mod and TFTR are analyzed, and ITER operation is considered.

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\end{abstract}

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\end{document}
