Analysis of radiation environment at divertor in helical reactor FFHR-d1
Analysis of radiation environment at divertor in helical reactor FFHR-d1
复制标题
螺旋反应堆FFHR-d1偏滤器辐射环境分析
DOI：
10.1016/j.fusengdes.2014.02.071
复制
发表时间：
2014
影响因子：
1.7
通讯作者：
H. Tamura
中科院分区：
文献类型：
--
作者：
T. Tanaka;A. Sagara;S. Masuzaki;M. Tokitani;T. Muroga;J. Miyazawa;T. Goto;H. Tamura
为了准确分析偏滤器区的中子学环境，对螺旋堆FFHR-d1的三维模型进行了中子输运计算。基于获得的中子谱，辐照损伤，接触剂量率和衰变热的大小已主要为铁，钨和铜进行了评估。由于偏滤器可以放置在螺旋反应堆的辐射屏蔽后面，外侧偏滤器的损伤和放射性活化程度几乎比包层第一壁低两个数量级。Cu材料可以用作外侧偏滤器的冷却通道材料。相比之下，由于内侧空间有限，内侧偏滤器的量级仅比第一壁的量级低一个数量级。运行6年后，铜的损伤估计为10 dpa。在偏滤器开发和反应堆设计方面的进一步努力可以将内侧偏滤器采用铜材料的损坏程度抑制到一半以下。
Neutron transport calculations with a three-dimensional model of the helical reactor FFHR-d1 have been performed for the accurate analysis of neutronics environment in the divertor areas. Based on the obtained neutron spectra, magnitudes of irradiation damage, contact dose rates and decay heat have been evaluated mainly for Fe, W and Cu. Since divertors can be placed behind radiation shields in helical reactors, magnitudes of damage and radioactivation at the outboard divertors are almost two orders lower than those at blanket first walls. Cu materials could be used as a cooling channel material of the outboard divertors. In contrast, the magnitudes at the inboard divertors are only one order lower compared with those at the first walls due to the limited space at the inboard side. Damage on Cu is evaluated to be ∼10 dpa after 6 years operation. Further efforts in divertor development and reactor design could suppress the magnitude of damage to less than half for adoption of Cu materials for the inboard divertors.
螺旋反应堆先进自冷液层系统的中子学研究
DOI：
--
发表时间：
2008
期刊：
Nuclear Fusion 48-035005
影响因子：
--
作者：
T. Tanaka;et. al.
通讯作者：
et. al.