Connections between physics and economics for Tokamak fusion power plants
Connections between physics and economics for Tokamak fusion power plants
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托卡马克聚变发电厂物理与经济学之间的联系
DOI：
10.1007/bf01108258
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发表时间：
1988
影响因子：
1.1
通讯作者：
J. Delene
中科院分区：
文献类型：
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作者：
R. Krakowski;J. Delene
利用托卡马克聚变反应堆的简化物理、工程和成本模型，定量地研究了物理性能和动力装置经济性之间的关系。本文所包含的材料是基于一系列约束方案、聚变燃料、包层/屏蔽配置、功率转换方案和商业最终产品对聚变的经济、安全和环境影响进行更广泛研究的一部分。只有DT-燃料托卡马克反应堆，通过中间热交换和传统的热电转换循环产生电力被认为是一个自冷却的锂金属毯钒合金结构，钢屏蔽，和超导磁体被用于所有的情况下研究。Troyon标度的乐观扩展应用于高伸长率（κ= 2.5）和低安全系数（q =2.3）等离子体，其中β=0.1和有效（IφPCD=0.2 A/W）电流驱动。这1200兆瓦（净）电厂提供了一个经济上有竞争力的基本情况下，比较其他方法的托卡马克聚变发电。选择用于比较的基本情况代表了对当前托卡马克物理和技术的乐观推断。应用系数βBφa/Iφ等于0.04的Troyon标度;还检查了随等离子体伸长而减小Troyon系数的特别但悲观的标度的影响。此外，假定在T =10 keV等离子体温度下，电流驱动效率为恒定值，λ =nIφRT/PCD=0.2 A/W;虽然相对于目前的经验，这代表了一个积极的研发目标，但对于基壳，特别是对于第二稳定区托卡马克，实现自举电流可以显著减少这个问题。还研究了恒定归一化电流驱动效率的影响和重新优化，即λ =nIφRT/PCD。虽然本研究的重点一直是乐观的basecase托卡马克，比较与托卡马克的基础上（a）在第二稳定区的操作（β=0.2，增加的纵横比，减小的伸长），（B）超高场但低β操作，（c）非常低的纵横比和高度伸长的球形环面，和（d）使用长脉冲的本数据库的直接应用，低β托卡马克一系列的基本情况下的参数和操作变量的经济影响进行检查，包括电流驱动效率，β，稳定性限制，先进的磁铁，规模经济，毯子/屏蔽寿命，毯子厚度，和工厂的交货时间。据发现，一系列的托卡马克的选择，相对于本研究所选择的乐观的基本情况下，可能会提供经济上有竞争力的电厂。物理和技术的进步，需要实现这一有吸引力的最终产品的定量阐明所有托卡马克的选择考虑。
A simplified physics, engineering, and costing model of a tokamak fusion reactor is used to examine quantitatively the connection between physics performance and power-plant economics. The material contained herein was generated as part of a broader study of the economic, safety, and environmental impact of fusion based on a range of confinement schemes, fusion fuels, blanket/shield configurations, power-conversion schemes, and commercial end products. Only a DT-fuelled tokamak reactor that produces electricity through an intermediate heat exchange and a conventional thermal-electric conversion cycle is considered; a self-cooled lithium-metal blanket with vanadium-alloy structure, steel shield, and superconducting magnets is used for all cases studied. An optimistic extension of Troyon scaling is applied to a high-elongation (κ= 2.5) and low-safety-factor (qψ=2.3) plasma with β=0.1 and efficient (IφPCD=0.2 A/W) current drive. This 1200-MWe (net) power plant provides an economically competitive base case with which to compare other approaches to tokamak fusion power. The base case chosen for comparisons represents an optimistic extrapolation of present tokamak physics and technology. Troyon scaling with a coefficientβBφa/Iφequal to 0.04 is applied; the impact of an ad hoc but pessimistic scaling that diminished the Troyon coefficient with plasma elongation was also examined. Additionally, a constant current-drive efficiency, ϒ=nIφRT/PCD=0.2 A/W, atT=10 keV plasma temperature is assumed; although representing an aggressive R&D target relative to present experience, the realization of bootstrap currents for the basecase, and especially for the second-stability-region tokamak, can significantly reduce this problem. The impact and reoptimization for a constant normalized current-drive efficiency, ϒ=nIφRT/PCD, was also examined. Although the focus of this study has been the optimistic basecase tokamak, comparisons are made with tokamaks based on (a) operation in the second-stability region (β=0.2, increased aspect ratio, reduced elongation), (b) super high-field but low-beta operation, (c) very low aspect ratio and highly elongated spherical torus, and (d) a direct application of the present database using a long-pulsed, low-beta tokamak. The economic impact of a range of base-case parameters and operating variables is examined, including current-drive efficiency, beta, stability limits, advanced magnets, economy of scale, blanket/shield lifetime, blanket thickness, and plant lead time. It is found that a range of tokamak options, relative to the optimistic base case selected for this study, may provide economically competitive power plants. Areas where physics and technology advances are needed to achieve this attractive end product are quantitively elucidated for all tokamak options considered.
影响因子：
3.3
作者：
M. Murakami;J. D. Callen;L. Berry
通讯作者：
M. Murakami;J. D. Callen;L. Berry
核工程设计/融合。
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