Feasibility Study of a Compact Ignition Tokamak Based upon GyroBohm Scaling Physics

Feasibility Study of a Compact Ignition Tokamak Based upon GyroBohm Scaling Physics
复制标题

基于陀螺玻姆尺度物理的紧凑点火托卡马克的可行性研究

DOI:
10.13182/fst03-a245
复制
发表时间:
2003
影响因子:
0.9
通讯作者:
C. Wong
C. Wong
中科院分区:
工程技术4区
文献类型:
--
作者:
C. Petty;J. Deboo;R. L. Haye;T. Luce;P. Politzer;C. Wong

文献摘要

参考文献

被引文献

相似文献

用标准ELMing H模等离子体设计一个小尺寸(R = 4.45m,BT = 5.04T)超导线圈点火托卡马克(Q = ∞)看来是可行的。该有效尺寸(BT 2/3R 5/6)小于Q = 10燃烧(D-T)等离子体实验的当前提议。在高β(β = 4.1%)条件下,从现有托卡马克数据库出发,沿沿着gyro-Bohm标度路径运行,使堆芯输运的损耗功率超过H模阈值功率,从而获得了这种小有效尺寸点火所需的良好约束。使用可以实现高归一化电流(Ip/aBT = 1.63)的设计也有助于减小机器的尺寸。这种相对紧凑的点火托卡马克的设计满足了对超导环向场线圈和中心螺线管的合理的工程约束,并允许足够长的燃烧时间使等离子体电流松弛到其最终状态。
The design of a reduced size (R = 4.45 m, BT = 5.04 T) ignition tokamak (Q = ∞) with superconducting coils using a standard ELMing H-mode plasma appears to be feasible. This effective size (BT2/3R5/6) is smaller than current proposals for Q = 10 burning (D-T) plasma experiments. The good confinement required for ignition with this small effective size is obtained by operating along a gyroBohm scaling path starting from the existing tokamak database at high beta (β = 4.1%) so that the loss power from core transport exceeds the H-mode threshold power. Using a design that can achieve a high normalized current (Ip/aBT = 1.63) also helps to decrease the size of the machine. The design of this relatively compact ignition tokamak satisfies reasonable engineering constraints on the superconducting toroidal field coils and central solenoid, and allows for a sufficiently long burn time for the plasma current to relax to its final state.
DOI: 10.1088/0029-5515/47/6/s01
发表时间: 2007-06-01
期刊: NUCLEAR FUSION
影响因子: 3.3
作者:
Shimada, M.;Campbell, D. J.;Sipps, A. C. C.
通讯作者: Sipps, A. C. C.