Overview of the ARIES-RS reversed-shear tokamak power plant study
Overview of the ARIES-RS reversed-shear tokamak power plant study
复制标题
ARIES-RS 反剪托卡马克发电厂研究概述
DOI：
10.1016/s0920-3796(97)00110-5
复制
发表时间：
1997
影响因子：
1.7
通讯作者：
C. Wong
中科院分区：
文献类型：
--
作者：
F. Najmabadi;C. Bathke;M. Billone;J. Blanchard;L. Bromberg;E. Chin;F. Cole;J. A. Crowell;D. Ehst;L. El;J. Herring;T. Hua;S. Jardin;C. Kessel;H. Khater;V. Lee;S. Malang;T. Mau;Ronald L. Miller;E. Mogahed;T. Petrie;E. Reis;J. Schultz;M. Sidorov;D. Steiner;I. Sviatoslavsky;D. Sze;R. Thayer;M. Tillack;P. Titus;Lester M Wagner;Xueren Wang;C. Wong
ARIES-RS托卡马克是一个概念性的，d - t燃烧1000兆瓦的发电厂。与早期的ARIES设计研究一样，ARIES- rs的最终设计是使用最佳可用的物理和工程模型以自一致的方式获得的。对单个系统以及系统接口和交互的详细分析被纳入ARIES系统代码中，以确保自一致性并朝着最低成本的系统进行优化。ARIES-RS设计采用反向剪切等离子体，并采用中等宽高比（a =4.0）。等离子体电流相对较低（Ip=11.32 MA），而自举电流分数较高（fBC=0.88）。因此，射频电流驱动所需的辅助功率相对较低（约80 MW）。同时，平均环面β很高（β=5%），提供接近实际工程极限的功率密度（峰值中子壁载荷为5.7 MW m−2）。环形场（TF）线圈系统采用相对“传统”的材料（Nb3Sn和NbTi导体与316SS结构）设计，并且在线圈的设计极限为~ 16 T时运行，以优化设计点。ARIES-RS设计采用自冷锂包层，结构材料为钒合金。v合金具有低活化、低余热、耐高温和处理高热流密度的特点。自冷式液态锂电毯结构简单，并且随着绝缘涂层的发展，具有较低的工作压力。此外，这种毛毯具有优异的中子性能。已经进行了详细的分析，以最大限度地降低成本，最大限度地提高毯子和屏蔽的性能。这种设计的一个显著特点是将第一道墙、保护层、部分屏蔽层、分流器和稳定壳整合为每个扇区内的一个整体单元。维修方案包括横向拆除整个扇区。在ARIES-RS研究启动之前，与美国电力公司和工业界的代表合作，制定了一套核聚变示范和商业发电厂的顶层要求和目标。描述了ARIES-RS达到这些要求和目标的程度以及必要的权衡，并介绍了高杠杆领域和关键研发项目。
The ARIES-RS tokamak is a conceptual, D–T-burning 1000 MWe power plant. As with earlier ARIES design studies, the final design of ARIES-RS was obtained in a self-consistent manner using the best available physics and engineering models. Detailed analyses of individual systems together with system interfaces and interactions were incorporated into the ARIES systems code in order to assure self-consistency and to optimize towards the lowest cost system. The ARIES-RS design operates with a reversed-shear plasma and employs a moderate aspect ratio (A=4.0). The plasma current is relatively low (Ip=11.32 MA) and bootstrap current fraction is high (fBC=0.88). Consequently, the auxiliary power required for RF current drive is relatively low (∼80 MW). At the same time, the average toroidal beta is high (β=5%), providing power densities near practical engineering limits (the peak neutron wall loading is 5.7 MW m−2). The toroidal-field (TF) coil system is designed with relatively `conventional' materials (Nb3Sn and NbTi conductor with 316SS structures), and is operated at a design limit of ∼16 T at the coil in order to optimize the design point. The ARIES-RS design uses a self-cooled lithium blanket with vanadium alloy as the structural material. The V-alloy has low activation, low afterheat, high temperature capability and can handle high heat flux. A self-cooled liquid lithium blanket is simple, and with the development of an insulating coating, has low operating pressure. Also, this blanket gives excellent neutronics performance. Detailed analysis has been performed to minimize the cost and maximize the performance of the blanket and shield. One of the distinctive features of this design is the integration of the first wall, blanket, parts of the shield, divertor and stability shells into an integral unit within each sector. The maintenance scheme consists of horizontal removal of entire sectors. Prior to the initiation of the ARIES-RS study, a set of top-level requirements and goals for fusion demonstration and commercial power plants was evolved in collaboration with representatives from US electric utilities and from industry. The degree to which ARIES-RS reached these requirements and goals and the necessary trade-offs are described and the high-leverage areas and key R&D items are presented.