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Radiation Resistance of a Structural Material Based on Modified Titanium Hydride
Science and Technology of Nuclear Installations ( IF 1.1 ) Pub Date : 2021-03-30 , DOI: 10.1155/2021/6658431
R. N. Yastrebinsky 1 , V. I. Pavlenko 1 , A. A. Karnauhov 1 , N. I. Cherkashina 1 , A. V. Yastrebinskaya 1 , A. I. Gorodov 1
Affiliation  

This work investigates the radiation resistance of a structural material based on modified titanium hydride and a Portland cement in a flux of neutron and γ-radiation. An assessment of the geometric and physicomechanical properties is given, along with the surface structure of irradiated cement composites, and the phase composition of the main hydrosilicates of the hydrated cement matrix during its γ-irradiation. It is shown that the use of a shot of titanium hydride increases the radiation resistance of radiation shielding based on a cement matrix, in comparison with the unmodified shot. A composite based on a modified shot of titanium hydride retains its basic properties after γ-irradiation, at an absorbed dose of up to 10 MGy. At an absorbed dose of 2 MGy in the Portland cement matrix of a composite based on a modified shot of titanium hydride, the formation of suolunite hydrosilicates occurs. It was established using X-ray fluorescence that, in the titanium hydride, a redistribution of the electron density occurs at an absorbed dose of γ radiation of 5 MGy, caused by structural phase changes due to the ongoing dehydrogenation processes.

中文翻译:

基于改性氢化钛的结构材料的抗辐射性

这项工作研究了基于改性氢化钛和波特兰水泥的结构材料在中子和γ辐射通量中的抗辐射性。给出了几何和物理力学性能的评估,以及辐照水泥复合材料的表面结构,以及水合水泥基质在γ辐照过程中主要氢硅酸盐的相组成。结果表明,与未改性的喷​​丸相比,使用氢化钛喷丸可以提高基于水泥基的辐射屏蔽层的抗辐射性。基于氢化钛修饰丸的复合材料在γ之后仍保持其基本性能-辐射,吸收剂量最高为10 MGy。在基于氢化钛改性喷丸的复合材料的波特兰水泥基体中,当吸收剂量为2 MGy时,会发生钠铝辉石水硅酸盐的形成。使用X射线荧光可以确定,在氢化钛中,由于正在进行的脱氢过程而引起的结构相变化,在5 MGy的γ射线吸收剂量下,电子密度发生了重新分布。
更新日期:2021-03-30
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