Tokamak: FTU

Pulse number: 12658

Contact person: G. Bracco (bracco@frascati.enea.it)

Institution: Associazione EURATOM-ENEA sulla Fusione Frascati (Roma) Italy

Date of shot: 13 May 1997

Analysis code: ODIN (equilibrium), EVITA(data collection and power balance)

Run number: EVITA case bracco-za

Date of analysis: 27 November 2001

Assumption made for analysis:
FTU has an almost circular palsma cross section. Elongation value is provided,
but triangularity and identation are set to 0.
Zeff profile is assumed flat and Zeff value is assumed constant in time, in agreement with
visible bremsstrahlung results.
q profile from the solution of the current diffusion equation using neoclassical
resistivity (the min q values match the MHD behaviour of the dicharge);
Ion temperature profile from the solution of the neoclassical power balance
(it matches the experimental neutron yield, taking into account error bars, at
t=0.1s when the value is high enough to be measured);
The plasma power balance is well known only in the central part of the plasma
column, where the ECRH power dominates largely the other terms.

Shot description, purpose of the experiment:
ECRH heating (325 kW) in the current ramp-up phase.

Publication:
"MHD activity in FTU plasmas with reversed magnetic shear" P. Buratti,  et al.
Plasma Phys. Control. Fusion 39 (1997) B383.

Additional information:
FTU tokamak has an almost circular cross section.
Toroidal limiter is in Molibdenum, the external poloidal limiter is in inconel.

The data cover the time interval from 0.051-0.116 s. The ECRH power is switched
on at t=0.055 s. The peak electron temperature attains almost 8 keV.
Impurity content is dominated by Nickel and Molibdenum. Mo density is 0.04
times the Ni density.

0D data:

0D data refer to t=0.090, during the ECRH pulse.
BEPMHD and BETMHD are computed using kinetic data.