E. Marmar, P. Acedoa, O. Batishchev,
R. Bengtsonb, R. L. Boivin, F. Bombardac,
X. Bonninb, P. Bonoli, C. Boswell,
R. Bravenecb, N. Bretzd, C. Changn,
C. Christensen, G. Cimad, W. Dorlandd,
J. Drakee, E. Eisnerb, G. Esserf,
M. Finkenthalg, C. Fiore, K. Fournierh,
T. Fredian, R. Gandyi, S. Gangadhara,
K. Gentleb, J. Goetz, R. Granetz, M. Greenwald,
H. Grieme, G. Hallock, J. Harkerb,
J. Heardi, J. Hosead, A. Hubbard,
I. Hutchinson, J. Irby, D. Johnsond, J. Ke,
J. Kesner, S. Krasheninnikov, B. LaBombard,
H. Lamelaa, B. LeBlancd, Y. Lin,
B. Lipschultz, S. Lisgoj, R. Maquedak,
M. Mayg, A. Mazurenko, S. Migliuolo,
E. Nelson-Melby, G. Miller, D. Mossessian,
R. Nachtrieb, R. Nazikiand, R. Neul,
H. Ohkawa, P. O'Shea, T. S. Pedersen,
D. Pappas, C. K. Phillipsd, A. Pigarov,
C. S. Pitcher, M. Porkolab, J. Ramos, J. Reardon,
J. Rice, B. N. Rogerse, J. C. Rost, W. Rowanb,
J. Schachter, G. Schillingd, H. Scotth,
C. Skinnerd, J. A. Snipes, V. Soukhanovskiig,
P. Stangebyj, P. Stek, J. Stillerman, Y. Takase,
G. Taylord, J. Terry, T. Tutt, M. Umansky,
W. Wamplerm, A. Wanh, C. Wattsi,
L. Weathers, J. Weavere, B. Welche,
J. R. Wilsond, S. Wolfe, K.-L. Wongd,
A. Woottonb, S. Wukitch, G. Wurdenk,
Y. In, H. Yuh, S. Zwebend
MIT Plasma Science and Fusion Center, Cambridge, MA 02139, USA
a Carlos III University, Madrid, Spain
b U. Texas, Austin, TX, USA
c ENEA Frascati, Italy
d Princeton Plasma Physics Lab., Princeton, NJ, USA
e U. Maryland, College Park, MD, USA
f KFA Julich, Germany
g Johns Hopkins U., Baltimore, MD, USA
h Lawrence Livermore National Lab., Livermore, CA, USA
i Auburn U., Auburn, AL, USA
j U. Toronto, Toronto, Ontario, Canada
k Los Alamos National Lab., Los Alamos, NM, USA
l MPIPP, Garching, Germany
m Sandia National Lab., Albuquerque, NM, USA
n Courant Institute of Mathematical Sciences, New York University,
New York, NY, USA
Abstract. Recent results from the compact, high field, Alcator C-Mod tokamak
program are summarized. H-mode threshold studies have demonstrated that the
threshold appears to be closely related to local edge plasma parameters: for
fixed field and plasma current,
Te() takes on a density
independent value at the transition. The Enhanced D-Alpha H-Mode (EDA) regime
has been investigated. EDA is distinct from ELM free H mode, in that there is
no accumulation of impurities, and at the same time EDA does not exhibit large
discrete ELMs. The energy confinement is degraded by only about 10%, compared
to ELM free. Comparisons for EDA with ELMy H-Mode database scalings indicate
EDA 1.2. Strong toroidal rotation is observed in
ICRF-only auxiliary heated plasmas; the rotation increases with plasma
pressure, and decreases with increasing plasma current. The inferred radial
electric field reaches the order of
30kV/m near the center of the
plasma. Through feedback controlled nitrogen impurity puffing, steady state
detached EDA H-Modes have been achieved with
Zeff < 1.5. is
reduced by about 10% in the detached case, compared to the confinement before
the
N2 puff begins. The heat load to the divertor is reduced by a
factor of 4. Volume recombination rates are measured in the divertor, using
2-d tomography of Balmer series TV movies. Volume recombination can be a
significant contributor to the overall reduction in ion current to the
divertor plates which occurs in detachment. Particle balance measurements
indicate that the divertor and main chamber plasmas are largely isolated from
one another, at least with regard to particle recycling, with most of the main
chamber (core plus scrape-off) fueling coming from neutrals in the main
chamber volume. With the addition of Lower Hybrid Current Drive, C-Mod would
be an ideal vehicle for investigation of advanced tokamak operation with fully
relaxed current profiles. Detailed modeling indicates that discharges
approaching the limit (
3.7) with > 70% bootstrap
fraction should be achievable.
IAEA 2001