IAEA Fusion Energy Conference 2010

Proceedings of the 23rd IAEA Fusion Energy Conference
Daejeon, 11-16 October 2010

Organized by the International Atomic Energy Agency
and hosted by the Government of the Republic of Korea


(ITR/P1-35) Integrated Modeling of Steady-State Scenarios and Heating and Current Drive Mixes for ITER

M. Murakami1), J.M. Park1), G. Giruzzi2), J. Garcia2), P. Bonoli3), R.V. Budny4), E.J. Doyle5), A. Fukuyama6), N. Hayashi7), M. Honda7), A. Hubbard3), S. Ide7), F. Imbeaux2), E.F. Jaeger1), T.C. Luce8), Y.S. Na9), T. Oikawa10), T.H. Osborne8), V. Parail11), A. Polevoi10), R. Prater8), A.C.C. Sips12), J. Snipes10), H.E. St. John8), P.B. Snyder8), I. Voitsekhovitch11), and the ITPA “Integrated Operations Scenarios” Topical Group
1) Oak Ridge National Laboratory, Oak Ridge, USA
2) CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France
3) Plasma Science and Fusion Center, MIT, Cambridge, Massachusetts, USA
4) Princeton Plasma Physics Laboratory, Princeton, New Jersey, USA
5) University of California, Los Angeles, California, USA
6) Graduate School of Engineering, Kyoto University, Kyoto, Japan
7) Japan Atomic Energy Agency, Naka, Ibaraki-ken, Japan
8) General Atomics, San Diego, California, USA
9) Dept Nuclear Engineering, Seoul National University, Seoul, Korea
10) ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul lez Durance, France
11) EURATOM/CCFE Fusion Association, Culham Sci. Centre, Abingdon, UK
12) EFDA-CSU, Culham Science Center, Abingdon, UK

Abstract.  Recent progress on ITER steady-state scenario modeling by the International Tokamak Physics Activity (ITPA)/Integrated Operation Scenario (IOS) Topical Group is reviewed. Code-to-code benchmarks as the IOS group's common activities for the two steady state scenarios (weak shear scenario and internal transport barrier scenario) are reviewed. These are discussed in terms of transport and kinetic profiles, heating and CD sources using various transport codes. Here weak magnetic shear scenarios integrate the plasma (core to edge) by combining a theory-base (GLF23) transport model with scaled experimental boundary profiles. The edge profiles (ρ = 0.8 - 1.0) are adopted from edge localized mode-averaged analysis of a DIII-D ITER Demonstration discharge. Uncertainties are estimated based on theoretical instability limits and experimental scaling laws, underscoring uncertainties in predicting pedestal and transport for ITER. A fully noninductive steady-state scenario is achieved with fusion gain Q = 3.4, noninductive fraction fNI = 1.01, bootstrap current fraction fBS = 0.64 and normalized beta βN = 2.8 at plasma current Ip = 8 MA and toroidal field BT = 5.3 T using ITER day-1 heating and current drive (CD) capability. Operation at 9 MA to achieve Q = 5 would lack 1-2 MA of noninductive current using the day-1 current drive systems. However, based on the calculated, fully-relaxed loop voltage, the long pulse operation goal (3000 s) with Q = 5 at Ip = 9 MA is possible if a sufficient flux (15-30 Weber) remains in the poloidal field system for the steady-state burn phase. A number of steady state scenarios with different heating and current drive mixes in a wide range of conditions were explored by exploiting the steady-state solution procedure for the GLF23 transport model. Source calculations in these simulations have been revised for electron cyclotron current drive including momentum conservation effects and for neutral beam current drive with finite orbit and magnetic pitch effects.

This work was supported by the US Department of Energy under DE-AC05-00OR22725, DE-AC02-09CH11466, DE-FG02-08ER54984, and DE-FC02-04ER54698.

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