JET_60931_com.dat = comments file for ITPA WDB Profile Database submission Tokamak: JET Pulse number: 60931 Shot description, purpose of the shot: Hybrid scenario at 1.7T/1.4MA, high triangularity, D2 gas puffing during heating phase, "compound" type 1 ELMs, no sawteeth, pair of 60927 Contact persons: Robert Budny, Irina Voitsekhovich, Ian Jenkins, Frederic Imbeaux, Emmanuel Joffrin Institution: EFDA-JET Date of shot: 20030309 Time of interest = 10.85s (50.85s in JET PPF time) for steady state 9-12s for high power heating phase Analysis codes: TRANSP and EFIT (for plasma boundary and q-profile) TRANSP RunID 60131C05 done at PPPL, stored at JET and on mdsplus server Date of analysis: 20080307 by Robert Budny(budny@princeton.edu) TRANSP run with new data Assumptions for analysis: Ti, toroidal rotation, Z_eff profiles from CX measurements Te and ne profiles from LIDAR measurements. Up/down asymmetric boundary and q-profile given by EFIT. TRANSP computes the central q to droop below unity, but no sawtooth are evident so the q_profile estimated by EFIT was used as input. Additional information: The TRANSP run C05 used reprocessed NBI data and corrected limiter position. The date of the reprocessed data was subsequent to that of the TRANSP run I02 used for the Ref 3 below. The NBI simulations (heating powere and NBCD) are similar. The q-profiles differ, and more smoothing of ne and Te was used in C05. The auxilliary heating consisted of D-NBI with power ramped up to 15.6MW from 6 to 14.5s and 1.7 MW H-minority ICRH from 6.0 to 17.5s The antenna phasing was -90,+90,-90,+90 degrees There was approx 1.2MW of LHCD from 1.8 to 6.0s The ICRH was modeled using New SPRUCE The LHCD was modeled using LSC The direction of the toroidal field and plasma current were in the normal JET direction - clockwise viewed from above. The NBI voltages were 105 keV for 6 beams, 90 for 2, and 78keV for 5 Argon and neon was injected into the plasma for diagnostic purposes. The measured densities were inputed into TRANSP All calculations have been done on a 40 zone radial grid. Most quantities have been smoothed to suppress statistical noise. In the jet_60931_2d.dat file thermal D is stored in NM1, trace T is stored in NM2 and the lumped impurity density in NM3. In the file jet_60931_0d.dat data is given at 10.85 secs. XPLIM is from XLOC; SEPLIM is given by EFIT. DELTA is the average of the upper and lower triangularities. The values for W_dia from TRANSP, EFIT, and XLOC are within 10% for the low power plateau and less than 5% for the high power plateau. The simulated DD neutron rate is high 35% The difference in density measurements between LIDAR and interferometry is within 22% Publications: 1) For a description of this and similar plasmas see A.C.C.Sips, E.Joffrin, et al, "Improved H-mode Identity Experiments in JET and ASDEX Upgrade", 30th EPS, St. Petersburg (2003) ECA Vol. 27A, O-1.3A 2) E.Joffrin, A.C.C.Sips, et al, "The 'hybrid' scenario in JET towards its validation for ITER", Nucl. Fusion <45> (2005), 626. 3) This shot was used for transport model testing by Frederic Imbeaux, et al, Plasma Phys. Cont. Fusion <47> (2005) B179 4) For a description of TRANSP analysis of JET plasmas see R.V. Budny, et al, "Local transport in Joint European Tokamak edge-localized, high confinement mode plasmas with H, D, DT, and T isotopes", Physics of Plasmas <7> (2000) 5038-5050.