Abstract
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.
Highlights
When designing a radiation protection structure, it is necessary to use materials that retain their operational properties under the influence of reactor irradiation
This paper presents the results of studies of the effect of high-energy c and neutron radiation on the structure and properties of a radiation protection material, based on a modified shot of titanium hydride and a Portland cement binder
Changes in density of most of these samples are within the volume determination error. us, this work did not reveal obvious changes in the geometric and physicomechanical properties of composites based on modified titanium hydride and Portland cement after neutron irradiation. ere does not appear to be a statistical significance
Summary
When designing a radiation protection structure, it is necessary to use materials that retain their operational properties under the influence of reactor irradiation (physicomechanical, physicochemical, structural, thermophysical, etc.). Is influence must be taken into account when building critical structures for radiation protection (nuclear and thermonuclear reactors, spacecraft, etc.) from ionizing radiation. E ability of materials to retain their basic properties after irradiation (within the specified range) is determined by the concept of radiation resistance. E quantitative characteristic is the maximum value of the absorbed radiation dose at which the material changes its properties to a subcritical level. E concept of the subcritical level depends on the specific operating conditions of the radiation-protective material. For materials operating in a stressed state, radiation resistance is determined by a decrease in strength characteristics, the specific value of which depends on the function performed by the material.
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