iter_10020100_com.dat = comments file for ITER Profile Database submission Tokamak: ITER Pulse number: 10020100 Scenario = 2 (ELMy H-mode), shot = 002 (Baseline), modeler = 01 (Budny), try = 00 Shot description,purpose of the shot: simulation of standard ITER H-mode based on GLF23 compare 10010100 = simulation of ITER H-mode based on ad hoc profiles Contact persons: Robert Budny (budny@princeton.edu) Institution: PPPL Date of shot: future Special times of interest 250.0 (20MW He3-minority ICRH and 33MW NNBI) 350.0 (33MW NNBI) Analysis codes: TSC, TRANSP TSC run number: iterH_011906 TRANSP run number: 20000T01 Date of analysis: 20080318 by Budny Assumptions made for analysis: TSC was used to model the startup and feedback during steady state. The plasma boundary evolved in time to a standard lower X-point configuration. The plasma current was ramped up linearly to 15MA at 100s. Steady state occurred near 160s. The GLF23 model is TSC was used to predict Te and Ti given fixed pedestal values at r/a=0.8. T_e and T_i with peaked profiles reached steady state central values of 26 and 23 keV respectively by 110s. n_e was assumed to have a near-flat profile, and was ramped to steady state with central value = 1.05e20/m3 at 160s. Be and Ar impurity density profiles were assumed to have the same profile as the electron density scaled down by 0.02 and 0.0012 respectively. The NUBEAM Monte Carlo package was used to model the deposition, excited-states ionization, pitch-angle scattering, slowing down, and heating of D-NNBI The injection energy was 1MeV with 16.5MW starting at 50s, increased to 33 MW at 100s. The NNBI was co-directed 35cm below the plasma magnetic axis with a tangency radius of 5.3m. NUBEAM also modeled the fusion alpha pitch-angle scattering, slowing down, and heating. ICRH is modeled using the TORIC package. The minority is assumed to be He3 with the same profile as the electron density scaled down by 0.01. the frequency is 52.5MHz and the power is ramped up starting at 160s to 20MW, then terminated at 290s Sawteeth are modeled with Kadomstev mixing at an assumed period of 50s. He4 ash accumulation is simulated assuming explicit diffusivity = 1.0 m2/s, inward pinch = -1 m/s, and wall/divertor recycling coefficient = 0.7 Additional information: The D species is NM1, the T species is NM2, and the Be and Ar impurities are lumped together as NM3. The D beam ion species is NFAST1 and the fusion He4 is NFAST2. Results from the TORIC ICRH code at 250s Antenna # 1 frequency = 52.5 MHz. thermal T harmonic 2 at R= 6.590 m. thermal D harmonic 1 at R= 4.929 m. thermal He4 harmonic 1 at R= 4.929 m. thermal Ar39_18 harmonic 1 at R= 4.520 m. thermal Be9_4 harmonic 1 at R= 4.346 m. fast D harmonic 1 at R= 4.929 m. *fast He3_min harmonic 1 at R= 6.590 m. fast He4_MCf harmonic 1 at R= 4.929 m. SPRUCE computed power fractions thermal T 13.9% thermal D 4.40% thermal He4 0.1% thermal Ar39_18 3.4% thermal Be9_4 1.8% fast He3_min 30.7% thermal elect 44.9% fast He4 0.5% fast D 0.2% mode conversion 0.0% In the file iter_10020100_0d.dat data is given at 250 secs. Publications: 1) For an analysis of a standard H-mode plasma in ITER-EDA, see "TRANSP simulations of International Thermonuclear Experimental Reactor plasmas", R.V.Budny, D.C.McCune, M.H.Redi, and R.M.Wieland, Physics of Plasmas, Vol 3 (1996) 4583-4593 2) For an analysis of a standard H-mode plasma in ITER-FEAT, see "Fusion alpha parameters in DT plasmas with high DT fusion rates", R.V.Budny, Nuclear Fusion <42> (2002) 1382. 3) For information on the use of TSC with TRANSP, see "Simulation and Analysis of the Hybrid Operating Mode in ITER", C.E.Kessel, R.V.Budny, and K.Indireshkumar, SOFE (2005)