jet_42982_com.dat = comments file for ITPA WDB Profile Database submission Tokamak: JET Pulse number: 42982 Shot description,purpose of the shot: ELMy with high DT fusion rate and yield Contact persons: Robert Budny (budny@princeton.edu) Institution: EFDA-JET Date of shot: 19971111 Times of interest 14.0s (54,0s in JET PPF time) for peak stored energy 16.4s (56.4s in JET PPF time) for peak neutron emission Analysis codes: TRANSP and EFIT (for plasma boundary) Run number: 42982C45 Date of analysis: 20080317 by Robert Budny This is a resubmission using TORIC for ICRH Assumptions made for analysis: Up/down asymmetric boundary given by EFIT. Ti, toroidal rotation velocity, and Zeff profiles from CX measurements. Te and Ne profiles from LIDAR measurements. 1D bulk radiation is used in radiation emission. Particle confinement time is calculated from source rates. q profile calculated in TRANSP from poloidal field diffusion and a sawtooth mixing model using sawtooth breaks observed in ece emission (KK242982.TF12). Additional information: Pulse #42982 set the record DT fusion energy yield with W_DT = 22 MJ. The main heating power was a mix of D and T NBI. The NBI voltages were 150 keV for 8 beams and 80keV for 8 He3-minority ICRH of 2.0MW with phasing -90,+90,-90,+90 degrees was also used. The Ti, rotation, and Zeff profiles were measured from 12 to 17.5s between R=3.4 and 3.75m. The Ti data was extrapolated in the core and edge for the TRANSP run. The direction of the toroidal field and plasma current were in the normal JET direction - clockwise viewed from above. 5000 Monte-Carlo ions were assumed for the beam ions and fast fusion alpha particles to minimize noise. In the file JET_42982_2d.dat data NM1, NM2, and NM3 are the caclulated densities of D, T, and average carbon and beryllium impurity ions. NFAST1 is the average of the D and T neutral beam ion densities. The file JET_42982_0d.dat data gives values at 14.0 and 16.4 secs. Values for elongation and triangularity in the 0d, 1d and 2d files are from the TRANSP output derived from the boundary input definition provided by EFIT. KAPA = (Zmax-Zmin)/(Rmax-Rmin), DELTA = (RGEO - min(R(zmin),R(Zmax)))/a XPLIM and SEPLIM are given by EFIT. as defined in the standard list of variables. The TRANSP run gives a simulated W_dia in good agreement with the measured values, and a neutron emission rate in good agreement with the measured values up to 15.0s, then 10-20% higher until the end of tne NBI. Publications: 1) For a general description of 42982 see L.D.Horton, et al. Nuclear Fusion <39> (1999) 993. 2) For an analysis of transport and use of the TRANSP code for 42982 and other JET ELMy H-mode plasmas see R.V.Budny, et al., "Local transport in Joint European edge-localized high-confinement mode plasmas with H, D, DT, and T isotopes", Phys. of Plasmas <7> (2000) 5038