Blanket and divertor design for force free helical reactor (FFHR)
Blanket and divertor design for force free helical reactor (FFHR)
复制标题
无力螺旋反应堆 (FFHR) 的包层和偏滤器设计
DOI：
10.1016/0920-3796(95)80005-i
复制
发表时间：
1995
影响因子：
1.7
通讯作者：
H. Tikaraishi
中科院分区：
文献类型：
--
作者：
A. Sagara;O. Motojima;Kiyomasa Y. Watanabe;S. Imagawa;H. Yamanishi;O. Mitarai;T. Satow;H. Tikaraishi
提出了无力螺旋反应堆包层和偏滤器的概念设计。与示范相关的FFHR是一种具有超导螺旋和极向线圈的日子型螺旋反应堆，该反应堆基于大型螺旋装置(LHD)，该装置目前正在美国国家核聚变科学研究所建造。FFHR的主要特点是螺旋线圈的无力配置，这使得我们可以简化线圈支撑结构，并使用强磁场来代替高等离子体β。以3GW热输出的自燃式D-T堆为目标，研究了LHD尺度下能量约束和密度限制下FFHR的设计参数。特别是，为了满足反应堆30年的寿命，讨论了FFHR的工程问题，重点讨论了500dpa的结构材料的选择，中子倍增器氚增殖系统的优化，熔盐流动冷却和包层工作温度，在超导线圈上实现辐射屏蔽以实现5个数量级以上的减少，以及效率约为30%的稳态氦除灰。
Conceptual design of blanket and divertor for a force free helical reactor (FFHR) is presented. The demonstration-relevant FFHR is a heliotron-type helical reactor having superconducting helical and poloidal coils based on the large helical device (LHD) which is now under construction in the National Institute for Fusion Science. The main feature of FFHR is force free configuration of helical coils, which allows us to simplify the coil supporting structure and to use high magnetic field instead of high plasma β. For the goal of a self-ignited D—T reactor of 3 GW thermal output, the design parameters for FFHR are investigated under the LHD scaling for energy confinement and density limit. In particular, to satisfy the reactor lifetime of 30 years, the engineering issues in FFHR are discussed by focusing on selection of structrual materials for 500 dpa, optimization of tritium breeding system with neutron multiplier, cooling with molten-salt Flibe and operation temperature in the blanket, radiation shielding to achieve a reduction of more than 5 orders of magnitude at superconducting coils, and steady state helium ash removal with an efficiency of around 30%.