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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >The design, fabrication and properties of B_4C/Al neutron absorbers
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The design, fabrication and properties of B_4C/Al neutron absorbers

机译:B_4C / Al中子吸收剂的设计,制备及性能

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摘要

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 B_4C/Al neutron radiation shielding material. The composition ratio for B_4C/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 B_4C 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.
机译:中子吸收器用于乏核燃料的存储或运输过程中的临界安全性。本文以B_4C / Al中子辐射屏蔽材料为基础,研究了具有良好机械性能和热中子吸收能力的金属基复合材料。首先设计了B_4C / Al复合材料的组成比,并计算了中子传输对材料厚度的依赖性。通过低温真空热压技术,制备了高浓度的B_4C中子吸收剂。此外,分析了相应的微观结构,物理,机械和腐蚀性能以及断裂表面,证明了所开发的复合材料能够像镉材料一样有效地屏蔽中子辐射。

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