这种中子屏蔽是由高质量／密度材料做成的，它能够很好地吸引中子。

The neutron shield is fabricated from a high mass/density material which provides a good source of neutron absorption

Boron carbide as high neutron absorption ability of material, has been widely used in nuclear reactors. In fast breeder reactor and the two advanced and high temperature gas-cooled reactor (DuiXing control on the choice of material and shielding materials, preferred the boron carbide as neutron absorption material, and has been successfully used.
Boron carbide (B4C) with high boron content, good chemical stability and high temperature resistance, especially its high neutron absorption cross section, the boron carbide is widely used as a control material in nuclear reactors. Boron carbide in the structure, chemical composition, manufacturing process and crystal structure and microstructure changes after radiation and its mechanism. For different reactors, the density of boron carbide are not the same.

碳化硼作为具有较高中子吸收能力的材料，已被广泛地应用在核反应堆中。在快中子增殖堆和和高温气冷堆这两种先进堆型的控制材料和屏蔽材料的选择上，首选了碳化硼作为中子吸收材料，而且得到了成功的应用。

碳化硼（B4C）具有高的硼含量、好的化学稳定性和耐高温性，特别是其高的中子吸收截面，使得碳化硼被广泛地用作核反应堆中的控制材料。碳化硼的结构、化学组成、制造工艺以及辐射后晶体结构和微观形貌的变化及其机理。对于不同的反应堆，碳化硼的密度是不一样的。

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