Integrated modelling of steady-state scenarios and heating and current drive mixes for ITER

Journal Article · Sat Jan 01 00:00:00 EST 2011 · Nuclear Fusion

DOI:https://doi.org/10.1088/0029-5515/51/10/103006· OSTI ID:1037095

Murakami, Masanori ^[1]; Park, Jin Myung ^[1]; Giruzzi, G ^[2]; Garcia, J ^[3]; Bonoli, P T ^[4]; Budny, R V ^[5]; Doyle, E J ^[6]; Fukuyama, A ^[7]; Ferron, J R ^[8]; Hayashi, N ^[9]; Honda, M ^[9]; Hubbard, A ^[10]; Hong, R M ^[8]; Ide, S ^[9]; Imbeaux, F ^[3]; Jaeger, Erwin Frederick ^[1]; Jernigan, Thomas C ^[1]; Luce, T C ^[8]; Na, Y S ^[11]; Oikawa, T ^[12] ; Osborne, T H ^[8]; Parail, V ^[13]; Polevoi, A ^[12]; Prater, R ^[14]; Sips, A C C ^[15]; Shafer, M W ^[16]; Snipes, J A ^[17]; John, H E ^[12]; Snyder, P B ^[8]; Voitsekhovitch, I ^[18]

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1. ORNL
2. CEA, IRFM, France
3. CEA Cadarache, St. Paul lex Durance, France
4. Massachusetts Institute of Technology (MIT)
5. Princeton Plasma Physics Laboratory (PPPL)
6. University of California, Los Angeles
7. Kyoto University, Japan
8. General Atomics, San Diego
9. Japan Atomic Energy Agency (JAEA), Naka
10. MIT Plasma Science & Fusion Center, Cambridge, MA 02139 USA
11. Seoul National University of Technology, Korea
12. ITER Organization, Saint Paul Lez Durance, France
13. Association EURATOM-CCFE, Abingdon, UK
14. General Atomics
15. Max Planck Institute for Plasma Physics, Garching, Germany
16. University of Wisconsin, Madison
17. ITER Organization, Cadarache, France
18. UKAEA Fusion, Culham UK

Recent progress on ITER steady-state (SS) scenario modelling by the ITPA-IOS group is reviewed. Code-to-code benchmarks as the IOS group's common activities for the two SS scenarios (weak shear scenario and internal transport barrier scenario) are discussed in terms of transport, kinetic profiles, and heating and current drive (CD) sources using various transport codes. Weak magnetic shear scenarios integrate the plasma core and edge by combining a theory-based transport model (GLF23) with scaled experimental boundary profiles. The edge profiles (at normalized radius rho = 0.8-1.0) are adopted from an edge-localized mode-averaged analysis of a DIII-D ITER demonstration discharge. A fully noninductive SS scenario is achieved with fusion gain Q = 4.3, noninductive fraction f(NI) = 100%, bootstrap current fraction f(BS) = 63% and normalized beta beta(N) = 2.7 at plasma current I(p) = 8MA and toroidal field B(T) = 5.3 T using ITER day-1 heating and CD capability. Substantial uncertainties come from outside the radius of setting the boundary conditions (rho = 0.8). The present simulation assumed that beta(N)(rho) at the top of the pedestal (rho = 0.91) is about 25% above the peeling-ballooning threshold. ITER will have a challenge to achieve the boundary, considering different operating conditions (T(e)/T(i) approximate to 1 and density peaking). Overall, the experimentally scaled edge is an optimistic side of the prediction. A number of SS scenarios with different heating and CD mixes in a wide range of conditions were explored by exploiting the weak-shear steady-state solution procedure with the GLF23 transport model and the scaled experimental edge. The results are also presented in the operation space for DT neutron power versus stationary burn pulse duration with assumed poloidal flux availability at the beginning of stationary burn, indicating that the long pulse operation goal (3000s) at I(p) = 9 MA is possible. Source calculations in these simulations have been revised for electron cyclotron current drive including parallel momentum conservation effects and for neutral beam current drive with finite orbit and magnetic pitch effects.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: DE-AC05-00OR22725
• OSTI ID: 1037095
• Journal Information: Nuclear Fusion, Vol. 51, Issue 10
• Country of Publication: United States
• Language: English