JET_38285_com.dat = comments file for ITPA WDB Profile Database submission Tokamak: JET Pulse number: 38285 Shot description,purpose of the shot: ELMy H-mode with high gas fueling Contact persons: Robert Budny, Jef Ongena, Xavier Garbet Institution: EFDA-JET Date of shot: 19960830 Time of interest = 18.39s (58.39s in JET PPF time) for steady state Analysis codes: TRANSP and EFIT (for plasma boundary) Run number: 38285C03 at PPPL (available via mdsplus) Date of analysis: 20051107 TRANSP run by Robert Budny (budny@princeton.edu) This is a resubmission updating variables Additional information: JET shot 38285 (2.5T, 2.5MA) is an ELMy H-mode shot with high gas fuelling obtained in a new JET pump divertor configuration. Plasma is deuterium in a single-null X-point configuration with the ion gradB drift pointing towards the X-point. About 6.0MW of 80KV/D and 6.0MW of 140KV/D neutral beam heating is turned on at 14 s (54 s in JET machine time). The beam heating is decreased from 19 secs and ceases at 20 secs. The direction of the toroidal field and plasma current were in the normal JET direction - clockwise viewed from above. In jet_38285_2d.dat the deuterium density is stored in NM1, trace H in NM2, and trace T in NM3. NM4 contains the carbon density being the majority impurity species. In the file JET_38285_0d.dat data its given at 18.39 secs. At that time, there is 11.5MW of beam heating and the plasma is in a steady ELMy H-mode phase. Values for kappa and delta in the 0d, 1d and 2d files are from the TRANSP output derived from the boundary input definition provided by EFIT. kappa = (Zmax-Zmin)/(Rmax-Rmin); delta = (RGEO - R(Zmax))/a XPLIM and SEPLIM from XLOC as defined in the standard list of variables. The 1d files for IP,VSURF and IBOOT have negative values as normal for JET. Some comments on this particular TRANSP run 38285 ESC equilibrium LEVGEO = 7 Up-down asymmetric boundary definition obtained from the EFIT program Early sawteeth events are taken into account in the simulation. Ti, v_phi, and Z_eff profiles from CX measurements between 14 and 19s. Te and Ne profiles vs. radius is from LIDAR measurements. 50 zones were used to resolve the thermal plasma profiles. Edge recycling and gas puffing used for particle balance to compute particle fluxes. The TRANSP run 38285C03 gives a simulated W_dia 20% lower than the measured and a simulated neutron yield 5% higher than the measured. Publications: 1) For details of this plasma see G.Matthews, et al EPS Berchtesgarten 1997 2) For description of TRANSP analysis of 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