Radiation-induced effects in neutron- and electron-irradiated lithium silicate ceramic breeder pebbles

Leys, Julia M.; Zariņš, A.; Cipa, Janis; Баумане, Л.; Ķizāne, Gunta; Knitter, Regina

doi:10.1016/j.jnucmat.2020.152347

Cited by 14 publications

(4 citation statements)

References 21 publications

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“…Numerous technological options are presently under examination for tritium production. Among these options is the utilization of lithium-containing ceramics, which generate tritium when subjected to neutron irradiation during nuclear reactions [6,7]. Furthermore, due to its mobility, tritium can be extracted from ceramics and promptly employed to sustain a thermonuclear reaction.…”

Section: Introductionmentioning

confidence: 99%

Study of the Resistance of Lithium-Containing Ceramics to Helium Swelling

Kozlovskiy,

Shlimas,

Borgekov

et al. 2024

Ceramics

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The paper presents the results of studies of the resistance of lithium ceramics to helium swelling during its accumulation in the structure of the near-surface layer, and the identification of the three types of lithium ceramics most resistant to radiation degradation: Li4SiO4, Li2TiO3, and Li2ZrO3. The simulation of helium swelling under high-dose irradiation was carried out by irradiation with He2+ ions with fluences of 1 × 1016 ion/cm2–5 × 1017 ion/cm2, which allows for simulating the implanted helium accumulation with a high concentration in the damaged surface layer (about 500 nm thick). The samples were irradiated at a temperature of 1000 K, the choice of which was determined by the possibility of simulating radiation damage as close as possible to real operating conditions. Such accumulation can result in the formation of gas-filled bubbles. Through the application of X-ray phase analysis, indentation testing, and thermophysical parameter assessments, it was ascertained that among the three ceramic types, Li4SiO4 ceramics exhibit the highest resistance to helium-induced swelling. These ceramics experienced less significant alterations in their properties compared to the other two types. An analysis of the correlation between the structural and strength parameters of lithium-containing ceramics revealed that the most significant changes occur when the volumetric swelling of the crystal lattice becomes the dominant factor in structural alterations. This phenomenon is manifested as an accelerated degradation of strength characteristics, exceeding 10%. At the same time, analysis of these alterations in the stability of thermophysical parameters to the accumulation of structural distortions revealed that, regardless of the type of ceramics, the degradation of thermophysical properties is most pronounced under high-dose irradiation (above 1017 ion/cm2).

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Section: Introductionmentioning

confidence: 99%

Study of the Resistance of Lithium-Containing Ceramics to Helium Swelling

Kozlovskiy,

Shlimas,

Borgekov

et al. 2024

Ceramics

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“…The use of layered structures, in particular carbide or nitride coatings, which are based on mechanisms for creating barrier effects, also helps to increase resistance to external influences, including ionizing radiation and mechanical stress [15,16]. An important factor in studying the mechanisms of radiation damage, in addition to dimensional factors, is the composition of structural materials that are used in nuclear physics installations, including for protection from the negative effects of neutron radiation, as well as products of nuclear reactions associated with their accumulation in the material of blankets [17,18]. A number of works [17][18][19] have shown that when irradiated with neutrons in lithium-containing ceramics used as blanket materials (for tritium multiplication), not only an accumulation of structural distortions occurs but also a change in the phase composition associated with polymorphic or transformation phase transformations, which are inextricably linked with the accumulation of radiolysis products.…”

Section: Introductionmentioning

confidence: 99%

“…An important factor in studying the mechanisms of radiation damage, in addition to dimensional factors, is the composition of structural materials that are used in nuclear physics installations, including for protection from the negative effects of neutron radiation, as well as products of nuclear reactions associated with their accumulation in the material of blankets [17,18]. A number of works [17][18][19] have shown that when irradiated with neutrons in lithium-containing ceramics used as blanket materials (for tritium multiplication), not only an accumulation of structural distortions occurs but also a change in the phase composition associated with polymorphic or transformation phase transformations, which are inextricably linked with the accumulation of radiolysis products. A number of works [20][21][22] also noted the role of boundary effects, a change in the concentration of which leads to a change in the rate of accumulation of radiation damage in ceramics as well as multilayer structures.…”

Section: Introductionmentioning

confidence: 99%

Study of Gas Swelling Processes under Irradiation with Protons and He2+ Ions in Li4SiO4–Li2TiO3 Ceramics

Kenzhina,

Kozlovskiy,

Chikhray

et al. 2023

Crystals

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One of the important areas of research in the energy sector is the study of the prospects for using new types of nuclear fuel, including tritium, which is one of the most promising types of fuel for thermonuclear energy. At the same time, for the production of tritium in the required quantities, the one that is the most optimal is the use of blanket materials based on lithium-containing ceramics. This is where tritium is released from lithium under the influence of neutron irradiation. The paper presents the results of an investigation of the influence of two-phase ceramics based on Li4SiO4–Li2TiO3 compounds on the resistance to external influences (mechanical loads) during the accumulation of hydrogen and helium (He2+) in the near-surface layer. The interest in such studies is primarily related to the search for solutions in the field of creating high-strength materials for tritium generation for its further use as nuclear fuel for thermonuclear fusion, as well as to the study of the mechanisms of the influence of different phases on the changes in the strength properties of ceramics, which provides an opportunity to expand fundamental knowledge in this area. The proposed method of obtaining two-phase ceramics by mechanical-chemical mixing and subsequent sintering into spherical particles enables the production of well-structured, high-strength ceramics of specified geometric dimensions (limited only by the dimensions of the mold) with a controlled phase ratio. During the experiments, it was found that increasing the content of Li4SiO4 phase in ceramics leads to an increase in strength characteristics (hardness, resistance to cracking) by 15–20% compared to single-phase ceramics. The most optimal composition of two-phase ceramics with high resistance to destructive embrittlement is the ratio of phases 0.75Li4SiO4–0.25Li2TiO3. One of the factors explaining the increase in resistance to destructive embrittlement under high-dose irradiation for two-phase ceramics is the increased dislocation density and the presence of interphase or intergranular boundaries, the high concentration of which leads to the creation of additional obstacles to the agglomeration of hydrogen and helium in the near-surface layer.

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“…Its high hydrogen content (up to 3.6 wt. %) and density (up to 3.8 g/cm 3 ) make it possible to effectively use titanium hydride to simultaneously attenuate both neutron and c radiation [28][29][30][31][32]. Previous reports [33][34][35][36][37][38] have shown that modification of the surface of titanium hydride shot with borosilicate coatings or ion-plasma spraying of titanium metal significantly increases its thermal stability.…”

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 effects in neutron- and electron-irradiated lithium silicate ceramic breeder pebbles

Cited by 14 publications

References 21 publications

Study of the Resistance of Lithium-Containing Ceramics to Helium Swelling

Study of the Resistance of Lithium-Containing Ceramics to Helium Swelling

Study of Gas Swelling Processes under Irradiation with Protons and He2+ Ions in Li4SiO4–Li2TiO3 Ceramics

Radiation Resistance of a Structural Material Based on Modified Titanium Hydride

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