Radiation-induced changes in the structure and mechanical properties of Fe–Mo alloy under electron irradiation

Tsepelev, A. B.; Ilyushin, A. S.; Kiseleva, T. Yu.; Brovkina, A F; Melnikov, V. N.

doi:10.1134/s2075113317030236

Cited by 4 publications

(3 citation statements)

References 5 publications

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“…The slightly lower hardness level of irradiated UFG and NC material is contrary to the usually observed radiation hardening in conventional structural materials. Radiation-induced softening was observed before in different materials [78][79][80][81] and is usually attributed to changes in composition or structure of the materials. Jiao et al [79] suggested radiation-induced grain growth and stress relaxations on grain boundaries as explanation for a softening effect in irradiated nanocrystalline ZrN films.…”

Section: Ufg and Nc Materialsmentioning

confidence: 99%

Impact of interfaces on the radiation response and underlying defect recovery mechanisms in nanostructured Cu-Fe-Ag

et al. 2018

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Section: Ufg and Nc Materialsmentioning

confidence: 99%

Impact of interfaces on the radiation response and underlying defect recovery mechanisms in nanostructured Cu-Fe-Ag

et al. 2018

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“…Materials intended for the radiation protection of nuclear power plants (NPP) must have a number of specific properties. First of all, this is a high efficiency of attenuation of neutron and gamma radiation, as well as radiation-thermal resistance [1][2][3][4][5][6][7][8]. Available and widely used in the protection of reactors, special concretes, being radiation and thermal resistant, at the same time, can not always provide the required protection efficiency.…”

Section: Introductionmentioning

confidence: 99%

Experimental Studies of Radiation-Protective Properties of a Modified Titanium Hydride

Karnauhov

Yastrebinskii

2022

MSF

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The results of experimental studies of the protective properties of titanium hydride with respect to neutron and gamma radiation in order to determine the optimal conditions for their use in the composition of the structural radiation protection of the nuclear reactor are presented. The weakening of the basic functionals in the thickness of protection, including the density of fast, intermediate and thermal neutrons, and the dose rate of gamma radiation is established. The functions of weakening the density of neutron flow and the dose rate of gamma radiation are measured in the conditions of "barrier" geometry. Determination of the protective properties of the structure was carried out when the modified titanium hydride fraction was placed in aluminum containers with a filling coefficient of a volume of container 0.63. The relaxation lengths for all neutron groups are close and on average are 9.8 cm. The functions of weakening the dose rate of gamma radiation of point sources Cs-137 and Co-60 are exponential. The weakening of radiation occurs with a constant relaxation length. For energy 0.661 MeV, the relaxation length is 7.1 cm, for energy 1.25 MeV, the relaxation length is equal to 10.1 cm. On the basis of the experimental studies, the high efficiency of the modified fraction of titanium hydride was confirmed during its use in protecting nuclear power plants.

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“…from ionizing radiation. Radiation-induced changes in mechanical properties is the result of a complex of various processes occurring in the structure of the material, including the formation of point defects and their accumulations (dislocation loops and pores); the formation of gaseous impurities (helium, hydrogen), stimulating gas swelling and embrittlement; decomposition of solid solutions; formation and dissolution of second phases; formation of radiation-stimulated diffusion and segregation of components; and radiation creep [1][2][3][4].…”

Section: Introductionmentioning

confidence: 99%

Radiation Resistance of a Structural Material Based on Modified Titanium Hydride

Yastrebinsky

Павленко

Karnauhov

et al. 2021

Science and Technology of Nuclear Installations

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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.

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Radiation-induced changes in the structure and mechanical properties of Fe–Mo alloy under electron irradiation

Cited by 4 publications

References 5 publications

Impact of interfaces on the radiation response and underlying defect recovery mechanisms in nanostructured Cu-Fe-Ag

Impact of interfaces on the radiation response and underlying defect recovery mechanisms in nanostructured Cu-Fe-Ag

Experimental Studies of Radiation-Protective Properties of a Modified Titanium Hydride

Radiation Resistance of a Structural Material Based on Modified Titanium Hydride

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