Prospects for pilot plants based on the tokamak, spherical tokamak and stellarator

被引：75

作者：

Menard, J. E. ^{[1
]}

Bromberg, L. ^{[2
]}

Brown, T. ^{[1
]}

Burgess, T. ^{[3
]}

Dix, D. ^{[4
]}

El-Guebaly, L. ^{[5
]}

Gerrity, T. ^{[2
]}

Goldston, R. J. ^{[1
]}

Hawryluk, R. J. ^{[1
]}

Kastner, R. ^{[4
]}

Kessel, C. ^{[1
]}

Malang, S. ^{[6
]}

Minervini, J. ^{[2
]}

Neilson, G. H. ^{[1
]}

Neumeyer, C. L. ^{[1
]}

Prager, S. ^{[1
]}

Sawan, M. ^{[5
]}

Sheffield, J. ^{[7
]}

Sternlieb, A. ^{[8
]}

Waganer, L. ^{[9
]}

Whyte, D. ^{[2
]}

Zarnstorff, M. ^{[1
]}

机构：

[1] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA

[2] MIT, Cambridge, MA 02139 USA

[3] Oak Ridge Natl Lab, Oak Ridge, TN USA

[4] Princeton Univ, Sch Engn & Appl Sci, Princeton, NJ 08544 USA

[5] Univ Wisconsin, Dept Engn Phys, Madison, WI USA

[6] Fus Nucl Technol Consulting, Linkenheim, Germany

[7] Univ Tennessee, Inst Secure & Sustainable Environm, Knoxville, TN USA

[8] Israel Minist Def, Tel Aviv, Israel

[9] Boeing Co, St Louis, MO USA

来源：

NUCLEAR FUSION | 2011年 / 51卷 / 10期

基金：

美国能源部;

关键词：

FUSION POWER-PLANT; TOROIDAL PLASMAS; CURRENT DRIVE; ARIES-ST; DESIGN; ITER; FACILITY; CONFINEMENT; NEUTRALIZER; LIMITS;

D O I：

10.1088/0029-5515/51/10/103014

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：

A potentially attractive next-step towards fusion commercialization is a pilot plant, i.e. a device ultimately capable of small net electricity production in as compact a facility as possible and in a configuration scalable to a full-size power plant. A key capability for a pilot-plant programme is the production of high neutron fluence enabling fusion nuclear science and technology (FNST) research. It is found that for physics and technology assumptions between those assumed for ITER and nth-of-a-kind fusion power plant, it is possible to provide FNST-relevant neutron wall loading in pilot devices. Thus, it may be possible to utilize a single facility to perform FNST research utilizing reactor-relevant plasma, blanket, coil and auxiliary systems and maintenance schemes while also targeting net electricity production. In this paper three configurations for a pilot plant are considered: the advanced tokamak, spherical tokamak and compact stellarator. A range of configuration issues is considered including: radial build and blanket design, magnet systems, maintenance schemes, tritium consumption and self-sufficiency, physics scenarios and a brief assessment of research needs for the configurations.

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