The design, fabrication and properties of B4C/Al neutron absorbers
The design, fabrication and properties of B4C/Al neutron absorbers
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DOI：
10.1016/j.jnucmat.2013.02.050
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发表时间：
2013-06
影响因子：
3.1
通讯作者：
Peng Zhang;Yuli Li;Wen-xian Wang;Zhanping Gao;B. Wang
中科院分区：
文献类型：
--
作者：
Peng Zhang;Yuli Li;Wen-xian Wang;Zhanping Gao;B. Wang
中子吸收体用于乏核燃料贮存或运输过程中的临界安全。本文以B4 C/Al中子辐射屏蔽材料为基础，研究了具有良好力学性能和热中子吸收能力的金属基复合材料。首次设计了B_4C/Al复合材料的成分配比，计算了中子透过率与材料厚度的关系。采用低温真空热压工艺制备了高B4 C含量的中子吸收体。并对相应的微观结构、物理力学性能、腐蚀性能和断口形貌进行了分析，证明所研制的复合材料能有效屏蔽中子辐射，与镉材料相当。
Neutron absorber is used for the criticality safety during the storage or transportation of spent nuclear fuel. In this work, the metal matrix composite with good mechanical property and thermal neutron absorbing ability was investigated based on B4C/Al neutron radiation shielding material. The composition ratio for B4C/Al composite was firstly designed and the dependence of the neutron transmission on the thickness of the material was calculated. By vacuum hot-pressing technique at a low temperature, the neutron absorbers with high concentration of B4C were fabricated. Furthermore, the corresponding microstructure, physical, mechanical and corrosion properties as well as fracture surface were analyzed, proving that the developed composites can shield the neutron radiation as effectively as cadmium materials.