Spherical torus: An approach to compact fusion at low field. Initial ignition assessments
Spherical torus: An approach to compact fusion at low field. Initial ignition assessments
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球形环面：一种低场紧凑聚变方法。
DOI：
10.13182/fst85-a40067
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发表时间：
1985
期刊：
影响因子：
--
通讯作者：
B. Riemer
中科院分区：
文献类型：
--
作者：
Y. Peng;D. Strickler;S. Borowski;W. R. Hamilton;R. Reid;J. Haines;V. Lee;G. Gorker;S. Kalsi;B. Riemer
基于球形环概念的点火装置的初步评估表明，点火球形环（IST）可以是高度成本效益和非常小的单位尺寸。假设先进的方法的电流驱动和约束和β缩放与等离子体电流，一个D-T IST与2至3 T的环形场估计有一个主半径范围从1米到1.6米，聚变功率小于60兆瓦。对于标称IST（2 T和1.6 m），根据聚变工程设计中心（FEDC）和成本算法，核岛的直接成本估计约为1.2亿美元，总直接成本约为3.4亿美元（按1984年中期美元计算）。对于具有较高字段和较小大小的IST（例如，在3 T和1 m），进一步减少核岛的成本估计。在约束缩放与等离子体尺寸的情况下，强等离子体顺磁性（自生磁场）的球形环仍然可以用来补偿预计的约束不足。由于适度的场强度，在IST概念中仅需要常规的工程方法，从而与常规的高场点火设计相比，导致显著的工程简化。独立式TF线圈/真空容器结构被评估为是可行的，并且相对独立于屏蔽结构和极向场线圈。这个名义IST的“独立”圆环的直接成本估计为7000万美元。这些非常有吸引力的项目的IST结果直接从一个可能的特殊功能的球形环等离子体的组合：高β，低β极向，自然大伸长率，高等离子体电流，强顺磁性，和托卡马克约束，这也把球形环在等离子体制度不同于传统的纵横比的托卡马克。实验测试的可行性的球形环面的概念建议。«少
Initial assessments of ignition devices based on the spherical torus concept suggest that an ignition spherical torus (IST) can be highly cost-effective and exceptionally small in unit size. Assuming advanced methods of current drive and confinement and beta scalings with plasma current, a D-T IST with a toroidal field of 2 to 3 T is estimated to have a major radius ranging from 1 m to 1.6 m, and a fusion power less than 60 MW. For the nominal IST (at 2 T and 1.6 m), the direct cost of the nuclear island is estimated to be about $120 M with a total direct cost about $340 M in mid-1984 dollars based on the Fusion Engineering Design Center (FEDC) and cost algorithm. For ISTs with higher field and smaller size (e.g., at 3 T and 1 m), further reductions of the cost of the nuclear island are estimated. In case of confinement scaling with the plasma size only, strong plasma paramagnetism (self-generated magnetic field) in the spherical torus may still serve to compensate for the projected confinement shortfall. Because of the modest field strength, only conventional engineering approaches are needed in the IST concepts, leading to dramatic engineering simplifications inmore » comparison wtih the conventional high-field ignition designs. A free-standing TF coil/vacuum vessel structure is assessed to be feasible and relatively independent of the shield structure and poloidal field coils. The direct cost of this 'stand-alone' torus of the nominal IST is estimated to be $70 M. These highly attractive projects of the IST result directly from a combination of the possible exceptional features of the spherical torus plasma: high beta, low beta poloidal, naturally large elongation, high plasma current, strong paramagnetism, and tokamak-like confinement, which also place the spherical torus in a plasma regime distinct from tokamaks of conventional aspect ratios. Experimental testing of the viability of the spherical torus concept is suggested.« less