Demonstration of ITER operational scenarios on DIII-D

被引:38
作者
Doyle, E. J. [1 ,2 ]
DeBoo, J. C. [3 ]
Ferron, J. R. [3 ]
Jackson, G. L. [3 ]
Luce, T. C. [3 ]
Murakami, M. [4 ]
Osborne, T. H. [3 ]
Park, J. -M. [4 ]
Politzer, P. A. [3 ]
Reimerdes, H. [5 ]
Budny, R. V. [6 ]
Casper, T. A. [7 ]
Challis, C. D. [8 ]
Groebner, R. J. [3 ]
Holcomb, C. T. [7 ]
Hyatt, A. W. [3 ]
La Haye, R. J. [3 ]
McKee, G. R. [9 ]
Petrie, T. W. [3 ]
Petty, C. C. [3 ]
Rhodes, T. L. [1 ,2 ]
Shafer, M. W. [9 ]
Snyder, P. B. [3 ]
Strait, E. J. [3 ]
Wade, M. R. [3 ]
Wang, G. [1 ,2 ]
West, W. P. [3 ]
Zeng, L. [1 ,2 ]
机构
[1] Univ Calif Los Angeles, Dept Phys & Astron, Los Angeles, CA 90095 USA
[2] Univ Calif Los Angeles, PSTI, Los Angeles, CA 90095 USA
[3] Gen Atom Co, San Diego, CA 92186 USA
[4] Oak Ridge Natl Lab, Oak Ridge, TN USA
[5] Columbia Univ, Dept Appl Phys & Appl Math, New York, NY USA
[6] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[7] Lawrence Livermore Natl Lab, Livermore, CA USA
[8] Euratom CCFE Fusion Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[9] Univ Wisconsin, Dept Energy Phys, Madison, WI USA
基金
英国工程与自然科学研究理事会;
关键词
PHYSICS BASIS; ENERGY; JET;
D O I
10.1088/0029-5515/50/7/075005
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
The DIII-D programme has recently initiated an effort to provide suitably scaled experimental evaluations of four primary ITER operational scenarios. New and unique features of this work are that the plasmas incorporate essential features of the ITER scenarios and anticipated operating characteristics; e. g. the plasma cross-section, aspect ratio and value of I/aB of the DIII-D discharges match the ITER design, with size reduced by a factor of 3.7. Key aspects of all four scenarios, such as target values for beta(N) and H-98, have been replicated successfully on DIII-D, providing an improved and unified physics basis for transport and stability modelling, as well as for performance extrapolation to ITER. In all four scenarios, normalized performance equals or closely approaches that required to realize the physics and technology goals of ITER, and projections of the DIII-D discharges are consistent with ITER achieving its goals of >= 400MW of fusion power production and Q >= 10. These studies also address many of the key physics issues related to the ITER design, including the L-H transition power threshold, the size of edge localized modes, pedestal parameter scaling, the impact of tearing modes on confinement and disruptivity, beta limits and the required capabilities of the plasma control system. An example of direct influence on the ITER design from this work is a modification of the physics requirements for the poloidal field coil set at 15 MA, based on observations that the inductance in the baseline scenario case evolves to a value that lies outside the original ITER specification.
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页数:8
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