Mission and Overview of a Fusion Development Facility

被引:10
作者
Garofalo, Andrea M. [1 ]
Chan, Vincent S. [1 ]
Stambaugh, Ron D. [1 ]
Smith, John P. [1 ]
Wong, Clement P. C. [1 ]
机构
[1] Gen Atom Co, San Diego, CA 92121 USA
关键词
Energy resources; fusion reactors; magnetic fields; neutron sources; physics; plasma devices; plasmas; proposals; tokamaks; DIII-D TOKAMAK; SPHERICAL TOKAMAK; H-MODE; DESIGN; PLASMA;
D O I
10.1109/TPS.2010.2040168
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 objective of the Fusion Development Facility (FDF) under consideration is to fill the gaps between ITER and current experiments and a fusion demonstration power plant (DEMO). FDF should carry forward advanced tokamak (AT) physics and enable development of fusion's energy applications. Near-term AT physics and nonsuperconducting magnet technology will be used to achieve steady state with burn, producing 100-250 MW fusion power with modest energy gain (Q < 5) in a modest sized device (between DIII-D and Joint European Torus). FDF will further develop all elements of AT physics for an advanced performance DEMO. With neutron flux at the outboard midplane of 1-2 MW/m(2), continuous operation for periods of up to two weeks, and a goal of a duty factor of 0.3 per year, FDF can produce fluences of 3-6 MW . year/m(2) in ten years of operation, for fusion nuclear component research and development. The development of blankets suitable for tritium, electricity, and hydrogen production will be done first in port modules. Then, the most promising candidates will be deployed as full blankets in FDF. Two to three full blankets and about a dozen port-blanket types could be tested. The goal of FDF is to demonstrate closure of the fusion fuel cycle, producing its own tritium. FDF, ITER, International Fusion Materials Irradiation Facility, and other AT devices will provide the basis for a fusion DEMO power plant of the ARIES-AT type.
引用
收藏
页码:461 / 467
页数:7
相关论文
共 25 条
[1]   The ITER design [J].
Aymar, R ;
Barabaschi, P ;
Shimomura, Y .
PLASMA PHYSICS AND CONTROLLED FUSION, 2002, 44 (05) :519-565
[2]   PHYSICS BASIS OF A FUSION DEVELOPMENT FACILITY UTILIZING THE TOKAMAK APPROACH [J].
Chan, V. S. ;
Stambaugh, R. D. ;
Garofalo, A. M. ;
Chu, M. S. ;
Fisher, R. K. ;
Greenfield, C. M. ;
Humphreys, D. A. ;
Lao, L. L. ;
Leuer, J. A. ;
Petrie, T. W. ;
Prater, R. ;
Staebler, G. M. ;
Snyder, P. B. ;
St John, H. E. ;
Turnbull, A. D. ;
Wong, C. P. C. ;
Van Zeeland, M. A. .
FUSION SCIENCE AND TECHNOLOGY, 2010, 57 (01) :66-93
[3]  
FESAC, 2007, PRIOR GAPS OPP LONG
[4]  
FOWLER RH, 1969, ORNLTM6845 OAK RIDG
[5]   Stability and control of resistive wall modes in high beta, low rotation DIII-D plasmas [J].
Garofalo, A. M. ;
Jackson, G. L. ;
La Haye, R. J. ;
Okabayashi, M. ;
Reimerdes, H. ;
Strait, E. J. ;
Ferron, J. R. ;
Groebner, R. J. ;
In, Y. ;
Lanctot, M. J. ;
Matsunaga, G. ;
Navratil, G. A. ;
Solomon, W. M. ;
Takahashi, H. ;
Takechi, M. ;
Turnbull, A. D. .
NUCLEAR FUSION, 2007, 47 (09) :1121-1130
[6]   Access to sustained high-beta with internal transport barrier and negative central magnetic shear in DIII-D [J].
Garofalo, A. M. ;
Doyle, E. J. ;
Ferron, J. R. ;
Greenfield, C. M. ;
Groebner, R. J. ;
Hyatt, A. W. ;
Jackson, G. L. ;
Jayakumar, R. J. ;
Kinsey, J. E. ;
La Haye, R. J. ;
McKee, G. R. ;
Murakami, M. ;
Okabayashi, M. ;
Osborne, T. H. ;
Petty, C. C. ;
Politzer, P. A. ;
Reimerdes, H. ;
Scoville, J. T. ;
Solomon, W. M. ;
John, H. E. St. ;
Strait, E. J. ;
Turnbull, A. D. ;
Wade, M. R. ;
VanZeeland, M. A. .
PHYSICS OF PLASMAS, 2006, 13 (05)
[7]  
Garofalo A.M., 2008, B AM PHYS SOC, V53, P192
[8]   1ST RESULTS FROM ALCATOR-C-MOD [J].
HUTCHINSON, IH ;
BOIVIN, R ;
BOMBARDA, F ;
BONOLI, P ;
FAIRFAX, S ;
FIORE, C ;
GOETZ, J ;
GOLOVATO, S ;
GRANETZ, R ;
GREENWALD, M ;
HORNE, S ;
HUBBARD, A ;
IRBY, J ;
LABOMBARD, B ;
LIPSCHULTZ, B ;
MARMAR, E ;
MCCRACKEN, G ;
PORKOLAB, M ;
RICE, J ;
SNIPES, J ;
TAKASE, Y ;
TERRY, J ;
WOLFE, S ;
CHRISTENSEN, C ;
GARNIER, D ;
GRAF, M ;
HSU, T ;
LUKE, T ;
MAY, M ;
NIEMCZEWSKI, A ;
TINIOS, G ;
SCHACHTER, J ;
URBAHN, J .
PHYSICS OF PLASMAS, 1994, 1 (05) :1511-1518
[9]  
KRITZ A., 1982, Proceedings of the 3rd International Symposium on Heating in Toroidal Plasmas, V2, P707
[10]   Optimum equilibria for high performance, steady state tokamaks [J].
Lin-Liu, YR ;
Stambaugh, RD .
NUCLEAR FUSION, 2004, 44 (04) :548-554