Influence of neutron irradiation on the strength characteristics of lithium ceramic pellets for fusion reactor blankets

Kapychev, V.; Tebus, V.; Фролов, В.

doi:10.1016/s0022-3115(02)01299-0

Cited by 6 publications

(4 citation statements)

References 3 publications

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“…From these viewpoints, ternary lithium-containing oxides such as Li 2 TiO 3 , Li 4 SiO 4 and LiAlO 2 are regarded as candidates. However, the generation and annihilation behaviors of irradiation defects in these materials, which should affect tritium release behavior [1,2] and material properties [3], are not understood sufficiently.…”

Section: Introductionmentioning

confidence: 99%

Derivation of potential model for LiAlO2 by simple and effective optimization of model parameters

Tsuchihira

Oda

Tanaka

2009

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 99%

Derivation of potential model for LiAlO2 by simple and effective optimization of model parameters

Tsuchihira

Oda

Tanaka

2009

Journal of Nuclear Materials

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“…An initial presumption can be made to explain this result [7]. Taking into account that the melting temperature of LiAlO 2 is 1.3 times that of silicate, and the helium retention in the test is more for LiAlO 2 than for silicate pellets, it is reasonable to suppose that the radiation resistance of aluminate pellets (and hence the constancy of the s compr value) is higher than that of silicate ones.…”

Section: Results Of Exposure To Reactor Irradiationmentioning

confidence: 99%

“…Measurements of helium-4 were performed under irradiation to determine the tritium balance; the results were discussed in [2,6]. The kinetic parameters of tritium and helium extraction from the irradiated pellets are shown in figure 3 [7]. The rate of helium release under reactor irradiation is much higher for Li 4 SiO 4 and Li 2 SiO 3 than for LiAlO 2 .…”

Section: Results Of Exposure To Reactor Irradiationmentioning

confidence: 99%

Research and development of lithium ceramics and models of tritium breeding zones for blankets in Russian reactor projects

Kapyshev

Chehlatov

Демидов

et al. 2004

Plasma Devices and Operations

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“…At the same 2 of 15 time, blank materials are subjected to significant temperature loads as well as high levels of neutron radiation, which can cause degradation and a decrease in the strength properties of these materials. Typically, lithium ceramics and structural materials are exposed to high temperatures and radiation loads during reactor operation [6][7][8]. High-temperature testing can markedly affect the degradation resistance and strength properties of lithiumcontaining ceramics, which are used as blanket materials for tritium breeding in fusion reactors [9].…”

Section: Introductionmentioning

confidence: 99%

The Influence of High-Temperature Tests on the Resistance to Degradation and Reduction in Strength Properties of Lithium-Containing Ceramics Used as Blanket Materials for Tritium Breeding

Kozlovskiy,

Moldabayeva,

Shlimas

et al. 2023

J. Compos. Sci.

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Conducting high-temperature tests on ceramics-containing lithium, which are employed as tritium breeding materials, plays a crucial role in comprehending their ability to withstand degradation and maintain their strength properties throughout operation. From the standpoint of fusion research, it is imperative to grasp these phenomena in order to guarantee the safety and effectiveness of reactors. Additionally, these factors could impact the choice of particular materials and designs for blanket materials. The primary objective of this research is to evaluate alterations in the strength characteristics of ceramics-containing lithium when subjected to high-temperature thermal stability tests, while also preserving the hardness stability and resistance to cracking in ceramics subjected to cyclic tests. Lithium-containing ceramics based on lithium titanate (Li2TiO3), lithium orthosilicate (Li4SiO4), and lithium methacyrconate (Li2ZrO3), having a high structural ordering degree and good strength properties, were chosen as objects for assessing resistance to high-temperature degradation. During the studies, it was discovered that the presence of interphase boundaries in the composition of ceramics linked to the development of impurity phases results in crack resistance growth during long-term high-temperature tests simulating the stress effect on the material. At the same time, an assessment of high-temperature aging as a result of modeling destruction processes showed that ceramics based on lithium metazirconate are the most resistant to degradation of strength properties. By simulating high-temperature aging processes, it became feasible to establish connections between structural alterations resulting from the thermal expansion of the crystal lattice and oxygen migration phenomena occurring at elevated temperatures. These factors collectively contribute to a detrimental reduction in the strength properties of ceramics-containing lithium.

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Influence of neutron irradiation on the strength characteristics of lithium ceramic pellets for fusion reactor blankets

Cited by 6 publications

References 3 publications

Derivation of potential model for LiAlO2 by simple and effective optimization of model parameters

Derivation of potential model for LiAlO2 by simple and effective optimization of model parameters

Research and development of lithium ceramics and models of tritium breeding zones for blankets in Russian reactor projects

The Influence of High-Temperature Tests on the Resistance to Degradation and Reduction in Strength Properties of Lithium-Containing Ceramics Used as Blanket Materials for Tritium Breeding

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