Applicability of Hydride Materials for Radiation Shielding in Helical Reactor FFHR-d1
Applicability of Hydride Materials for Radiation Shielding in Helical Reactor FFHR-d1
复制标题
氢化物材料在螺旋反应堆FFHR-d1中辐射屏蔽的适用性
DOI：
10.13182/fst15-110
复制
发表时间：
2015
影响因子：
0.9
通讯作者：
A. Sagara
中科院分区：
文献类型：
--
作者：
Teruya Tanaka;H. Muta;Y. Hishinuma;H. Tamura;T. Muroga;A. Sagara
在螺旋反应堆FFHR - d1设计中研究了氢化物屏蔽材料的性能和适用性。对于堆内和堆外使用，ZrH₂和TiH₂在快中子屏蔽方面的性能接近WC（在候选材料中最有效）。研究证实，两层铁素体钢（FS）/ZrH₂或TiH₂屏蔽层的中子屏蔽性能与总厚度相同的单层ZrH₂或TiH₂屏蔽层相似。这种屏蔽特性是与FFHR - d1结构设计保持一致的重要特征。在弯曲管道中对来自芯部等离子体的直接中子的衰减方面，氢化物管道壁与FS + B₄C和WC管道壁相比表现出更优的性能。虽然特别是对于堆内使用需要控制冷却气体的温度（<300°C）和氢浓度，但与其他候选材料相比，较低的重量密度和接触剂量率的快速衰减将是选择这些氢化物屏蔽材料的原因。
Abstract Performance and applicability of hydride shielding materials are investigated in the helical reactor FFHR-d1 design. Performance of ZrH2 and TiH2 in fast neutron shielding are close to that of WC, which is most effective among candidate materials, for both in-vessel and out-vessel use. The investigation confirms that neutron shielding performance of a two-layered ferritic steel (FS)/ZrH2 or TiH2 shield is similar to that of a one-layered ZrH2 or TiH2 shield with the same total thickness. This shielding property is an important feature to maintain consistency with the structure design of FFHR-d1. In attenuation of direct neutrons from the core plasma in a bending duct, the hydride duct walls show superior performance compared with FS + B4C and WC duct walls. While controls for temperature (at <300 °C) and hydrogen concentration in the coolant gas would be required particularly for in-vessel use, the lower weight densities and quick decay of contact dose rates compared with other candidate materials would be reasons to select these hydride shielding materials.