The influence of the long-term heating under H2 atmosphere on the tritium release behavior from the neutron-irradiated Li2TiO3

Ipponsugi, Akito; Katayama, Kazunari; Hoshino, Tsuyoshi

doi:10.1016/j.fusengdes.2021.112495

Cited by 6 publications

(3 citation statements)

References 18 publications

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“…To investigate the effects of long-term heating on the release behavior of tritium, Li 2 TiO 3 was irradiated by neutrons [109]. The authors stated that the tritium released at temperatures higher than 900 • C could not be recovered.…”

Section: Neutron Irradiationmentioning

confidence: 99%

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Recent Progress in Research of Solid Tritium Breeder Materials Li2TiO3: A Review

Chen

Wang

2022

Coatings

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During the past decades, fusion reactor fuels such as deuterium and tritium have been extensively investigated due to increasing interest in nuclear fusion energy. Tritium, which is scarce in nature, needs to be fabricated by tritium breeder materials. Among the commonly investigated tritium breeder materials, lithium titanate (Li2TiO3) is recognized as one of the most promising solid tritium breeder materials because of its considerable lithium (Li) atomic density, low activation, excellent chemical stability, and low-temperature tritium release performance. This paper aims to provide a systematic review of the current progress in Li2TiO3 preparation methods as well as the high Li density, tritium release performance, irradiation behavior, and modification technologies of Li2TiO3 pebbles. Li2TiO3 can be synthesized by strategies such as solid-state, sol–gel, hydrothermal, solution combustion synthesis, and co-precipitation methods. Among them, the hydrothermal method is promising due to its simplicity and low cost. Many researchers have begun to focus on composite ceramic pebbles to further improve tritium breeder performance. This will provide a new direction for the future development of Li2TiO3 pebbles. The present review concludes with a summary of the preparation methods currently under development and offers an outlook of future opportunities, which will inspire more in-depth investigation and promote the practical application of Li2TiO3 in this field.

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Section: Neutron Irradiationmentioning

confidence: 99%

“…(b) Raman spectra of Li2TiO3 irradiated with the 80 MeV O and 160MeV Xe ions, and of Li2TiO3 before irradiation. Reprinted with permission from ref [109]…”

mentioning

confidence: 99%

Recent Progress in Research of Solid Tritium Breeder Materials Li2TiO3: A Review

Chen

Wang

2022

Coatings

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“…The accumulation of reaction products, as well as the probable filling of pores by them, the presence of which can be caused both by the synthesis processes and tritium burnout, can lead to the destruction of ceramics, deterioration of their properties, decrease in mechanical stress and crack resistance. Such consequences can have a negative effect on the service life of lithium-containing ceramics, as well as reduce the tritium production efficiency [26][27][28][29]. In this connection, in recent years, great interest has been paid to experimental work related to the study of the radiation resistance of lithium-containing ceramics in the processes of hydrogenation, gas swelling, or helium embrittlement, the results of which will provide a more complete picture of the mechanisms and processes occurring in ceramics during radiation damage.…”

Section: Introductionmentioning

confidence: 99%

Study of Structural and Strength Changes in Lithium-Containing Ceramics—Potential Blanket Materials for Nuclear Power, Subjected to High-Dose Proton Irradiation

et al. 2022

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The paper considers the hydrogenation processes in Li2TiO3 ceramics under irradiation with protons with an energy of 500 keV and fluences of 1 × 1010–5 × 1017 ion/cm2. The choice of the type of irradiation, as well as the irradiation fluences, is based on the possibilities of modeling hydrogenation processes and studying the kinetics of structural changes caused by the accumulation of radiation damage. The choice of Li2TiO3 ceramics as objects of research is due to their prospects for using as blanket materials of thermonuclear reactors for the tritium production and accumulation. It was found that the formation of point defects and their subsequent evolution associated with the formation of complex compounds and the filling of pores, followed by the formation of gas-filled bubbles, the presence of which leads to a decrease in crack resistance and resistance to destruction of the near-surface layer. Based on the data on structural changes and evolution of the crystal lattice parameters, its swelling, a description of the destruction processes associated with hydrogenation in Li2TiO3 ceramics was proposed. Also, during the studies, it was found that at irradiation fluences above 1 × 1017 ion/cm2, the appearance of impurity inclusions characteristic of the TiO2 phase was observed, the presence of which indicates the crystal lattice destruction processes because of accumulation of radiation damage and deformations caused by them. Critical doses are established at which there is a sharp deterioration in strength and crack resistance, reflecting the resistance of ceramics to mechanical external influences.

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A DFT + U study on diffusion and aggregation behavior of He atoms in Li2TiO3

Zhou

Deng

2023

Computational Materials Science

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The influence of the long-term heating under H2 atmosphere on the tritium release behavior from the neutron-irradiated Li2TiO3

Cited by 6 publications

References 18 publications

Recent Progress in Research of Solid Tritium Breeder Materials Li2TiO3: A Review

Recent Progress in Research of Solid Tritium Breeder Materials Li2TiO3: A Review

Study of Structural and Strength Changes in Lithium-Containing Ceramics—Potential Blanket Materials for Nuclear Power, Subjected to High-Dose Proton Irradiation

A DFT + U study on diffusion and aggregation behavior of He atoms in Li2TiO3

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