JET_43002_com.dat = comments file for ITPA WDB Profile Database submission
 
  Tokamak: JET

  Pulse number: 43002

  Shot description,purpose of the shot: 
     ELMy with high DT fusion rate and yield

  Contact persons: Robert Budny,  Jef Ongena, Xavier Garbet

  Institution:  EFDA-JET

  Date of shot: 19971129

  Time of interest = 20.5s (60.5s in JET PPF time) for steady state

  Analysis codes: TRANSP and EFIT (for plasma boundary)

  Run number: 43002C59

  Date of analysis: 20051103 by Robert Budny (budny@princeton.edu)
  This is a resubmission fixing NM4

 Assumptions made for analysis:

  Up/down asymmetric boundary given by EFIT.
  Ti and toroidal rotation velocity profiles from CX measurements.
  Both the core (CXSM) and edge (CXSE) measurements were combined.
  Te and Ne profiles vs. radius from LIDAR measurements.
  Density of 2 impurity species (Be, and C) were used to produce a Zeff profile. 
  The radiation emission profile was derived from inverting two bolometry views.
  Particle confinement time is calculated from source rates.
  q profile calculated in TRANSP from the sawtooth mixing model and poloidal 
  field diffusion.

 Additional information:

  Pulse #43002 was dominantly T from the NBI and gas puff.

  The Ti, rotation, and Zeff profiles were measured from 17 to 22.3s
  between R=2.95 and 3.81m.

  The direction of the toroidal field and plasma current were in the
  normal JET direction - clockwise viewed from above.

  All beam related quantities (energy, particle sources, currents etc) 
  have been smoothed to suppress Monte-Carlo noise. 

  In jet_43002_2d.dat the trace hydrogen is stored in NM1, deuterium in NM2, 
  and tritium in NM3.
  NM4 contains the measured Be and carbon impurities.

  In the file JET_43002_0d.dat data is given at 20.50 secs. 

  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 - 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 15% above the measured value
  and a neutron emission rate high 8-30%.

 Publications:  
    1) For general description of high density JET ELMy H-mode plasmas see
       G. Saibene, et al, "Improved performance of ELMy H-mode
       at high density by plasma shaping in JET", Plasma Physics
       Controlled Fusion <44> (2002) 1769-1799,
    2) For an analysis of transport and microturbulence linear stability 
       in this plasma see
       R.V.Budny, et al., "Local physics basis of confinement degradation
       in JET ELMy H mode plasmas and implications for tokamak reactors"
       Nuclear Fusion <42> (2002) 66.
    3) For a description of TRANSP analysis of JET ELMy H-mode 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.