Study of safety concept for a helical-type fusion reactor, FFHR
Study of safety concept for a helical-type fusion reactor, FFHR
复制标题
螺旋型聚变反应堆FFHR安全概念研究
DOI：
10.1016/s0920-3796(97)00174-9
复制
发表时间：
1998
影响因子：
1.7
通讯作者：
T. Noda
中科院分区：
文献类型：
--
作者：
T. Uda;A. Sagara;O. Motojima;H. Yamanishi;Satoru Tanaka;T. Terai;T. Noda
介绍了一种无力螺旋反应堆（FFHR）的安全概念，它的概念设计与大螺旋装置（LHD）的建造并行进行。预计FFHR的主要安全特性是，稳定的等离子体运行，没有危险的电流中断，以及为氚增殖器选择熔盐Flibe毯，该毯具有低氚库存，自冷却效果和低化学活性。毡层达到如此高的温度，氚的渗透率增加，必须不断地回收这些氚。那么第一面墙的氚含量应该很低。通过对电站系统和部件的分类分析，表明高迁移率和伴随能量释放的大放射性泄漏事故是可以避免的。基本安全将得到多重保护系统的保障。为了防止因任何大型放射性约束元件断裂而导致的严重事故升级，提出了被动可靠的主动保护系统。因此，FFHR将被设计得尽可能安全。
Safety concepts for a force free helical reactor (FFHR), of which conceptual designs have been studied in parallel with the construction of the large helical device (LHD), are presented. The main safety features expected for the FFHR are, steady-state plasma operation, no dangerous current disruptions, and the selection of a molten-salt Flibe blanket for a tritium breeder which has low tritium inventory, self cooling effect and low chemical activity. The blanket reaches such high temperatures that the tritium permeation rate increases and this tritium must be continuously recovered. Then the first wall is expected to have a low tritium inventory. Based on the classification of the plant systems and components, it is shown that the high mobility and large radioactivity release accident accompanied with the energy release is avoidable. Fundamental safety would be secured by multiple protection systems. To prevent escalation to a severe accident caused by the fracture of any of the large radioactivity confinement components, passive and reliable active protection systems are proposed. Thus, FFHR will be designed to be as safe as possible.
O.Motojima：《超导大型螺旋装置的工程设计研究》核聚变。
DOI：
--
发表时间：
--
期刊：
影响因子：
--
作者：
通讯作者：
--