The ARIES-AT advanced tokamak, advanced technology fusion power plant

被引:175
作者
Najmabadi, F
Abdou, A
Bromberg, L
Brown, T
Chan, VC
Chu, MC
Dahlgren, F
El-Guebaly, L
Heitzenroederd, P
Henderson, D
St John, HE
Kessel, CE
Lao, LL
Longhurst, GR
Malang, S
Mau, TK
Merrill, BJ
Miller, RL
Mogahed, E
Moore, RL
Petrie, T
Petti, DA
Politzer, P
Steiner, D
Synder, P
Syaebler, GM
Turnbull, AD
Tillack, MS
Waganer, LM
Wang, X
West, P
Wilson, P
机构
[1] Univ Calif San Diego, Ctr Energy Res, La Jolla, CA 92093 USA
[2] Univ Wisconsin, Fus Technol Inst, Madison, WI 53706 USA
[3] MIT, Plasma & Fus Ctr, Cambridge, MA 02139 USA
[4] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[5] Gen Atom Co, San Diego, CA 92186 USA
[6] EG&G Idaho Inc, Idaho Natl Engn Lab, Fus Safety Program, Idaho Falls, ID 83415 USA
[7] Rensselaer Polytech Inst, Troy, NY 12180 USA
[8] Boeing Co, St Louis, MO 63166 USA
关键词
fusion power plant; tokamak; reversed shear plasma;
D O I
10.1016/j.fusengdes.2005.11.003
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The ARIES-AT study was initiated to assess the potential of high-performance tokamak plasmas together with advanced technology in a fusion power plant and to identifying physics and technology areas with the highest leverage for achieving attractive and competitive fusion power in order to guide fusion R&D. The 1000-Mwe ARIES-AT design has a major radius of 5.2 m, a minor radius of 1.3 m, a toroidal beta of 9.2% (beta(N) = 5.4) and an on-axis field of 5.6 T. The plasma current is 13 MA and the current-drive power is 35 MW. The ARIES-AT design uses the same physics basis as ARIES-RS, a reversed-shear plasma. A distinct difference between ARIES-RS and ARIES-AT plasmas is the higher plasma elongation of ARIES-AT (K-X = 2.2) which is the result of a "thinner" blanket leading to a large increase in plasma P to 9.2% (compared to 5% for ARIES-RS) with only a slightly higher beta(N). ARIES-AT blanket is a simple, low-pressure design consisting of SiC composite boxes with a SiC insert for flow distribution that does not carry any structural load. The breeding coolant (Pb-17Li) enters the fusion core from the bottom, and cools the first wall while traveling in the poloidal direction to the top of the blanket module. The coolant then returns through the blanket channel at a low speed and is superheated to similar to 1100 degrees C. As most of the fusion power is deposited directly into the breeding coolant, this method leads to a high coolant outlet temperature while keeping the temperature of the SiC structure as well as interface between SiC structure and Pb-17Li to about 1000 degrees C. This blanket is well matched to an advanced Brayton power cycle, leading to an overall thermal efficiency of similar to 59%. The very low afterheat in SiC composites results in exceptional safety and waste disposal characteristics. All of the fusion core components qualify for shallow land burial under U.S. regulations (furthermore, similar to 90% of components qualify as Class-A waste, the lowest level). The ARIES-AT study shows that the combination of advanced tokamak modes and advanced technology leads to an attractive fusion power plant with excellent safety and environmental characteristics and with a cost of electricity (4.7 c/kWh), which is competitive with those projected for other sources of energy. (c) 2005 Elsevier B.V. All rights reserved.
引用
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页码:3 / 23
页数:21
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