The Effect of Water on Tritium Release Behavior from Solid Breeder Candidates

Suematsu, Koichi; Nishikawa, Masabumi; Fukada, Satoshi; Kinjyo, T.; Koyama, Tomoyuki; Yamashita, Naoya

doi:10.13182/fst08-a1878

Cited by 9 publications

(3 citation statements)

References 8 publications

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“…Finally, the amount of chemical absorbed water and generated water per unit surface area for various ceramic breeder materials are shown in Fig. 5 [21,22,[26][27][28]. It can be seen from Fig.…”

Section: (B) and (D))mentioning

confidence: 97%

Mass Transfer Behavior and Microstructure Evolution of Li4TiO4-Li2TiO3 Core-shell Breeding Ceramic Under Harsh Operating Conditions

Chen

Katayama

et al. 2021

Preprint

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The development of novel tritium breeding materials was urgently needed in order to continuously optimize the tritium breeding ratio (TBR) of thermonuclear fusion reactors. From this point of view, Li4TiO4-Li2TiO3 core-shell breeding materials with more reasonable structure and theoretical Li density of 0.464 g/cm3 were prepared in this work. Notably, the mass transfer experiment at 900 °C in 1% H2/Ar shows that the theoretical Li density of this core-shell material after heating for 30 days was significantly higher than that of other breeding materials, indicating that it can provide more stable and efficient TBR. Specifically, the Li mass loss of the sample after 30 days heating was 3.4%, resulting in a decrease of Li density to 0.415 g/cm3. The mechanism of Li mass loss in Li4TiO4-Li2TiO3 core-shell breeding materials was investigated in detail. Moreover, the samples did not crack or collapse during the long-term heating process, and always maintained a satisfactory crushing load, revealing that this core-shell breeding ceramic can be used for a long time under severe operating conditions.

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Section: (B) and (D))mentioning

confidence: 97%

Mass Transfer Behavior and Microstructure Evolution of Li4TiO4-Li2TiO3 Core-shell Breeding Ceramic Under Harsh Operating Conditions

Chen

Katayama

et al. 2021

Preprint

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“…It has been reported by the present authors that water is released to the purge gas from solid breeder materials and this water affects the tritium release behavior by desorption of physical and chemical adsorbed water and water generation reaction [1][2][3][4]6]. It is necessary to understand the chemical forms of tritium and the amount of the water in the purge gas for designs of the tritium recovery system, because recovery of almost all bred tritium is expected to keep the tritium balance in a fusion reactor.…”

Section: Introductionmentioning

confidence: 92%

“…It is necessary to understand the chemical forms of tritium and the amount of the water in the purge gas for designs of the tritium recovery system, because recovery of almost all bred tritium is expected to keep the tritium balance in a fusion reactor. The tritium release model from solid breeder materials (Li 4 SiO 4 , Li 2 TiO 3 , LiAlO 2 , and Li 2 ZrO 3 ) has been developed by the present authors [1][2][3]7]. It was also reported by the present authors that tritium release curves estimated using the model gave a good agreement with the tritium release curves obtained not only from out-pile tritium release experiments by the present authors but also various other inpile tritium release experiments for each solid breeder materials under various purge gas conditions [3].…”

Section: Introductionmentioning

confidence: 99%

Effect of surface water on tritium release behavior from Li4SiO4

Hanada¹,

Fukada²,

Nishikawa³

et al. 2010

Fusion Engineering and Design

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a b s t r a c tThe tritium release model to represent the release behavior of bred tritium from solid breeder materials has been developed by the blanket group of Kyushu University. It has been found that water is released to the purge gas from solid breeder materials and that this water affects the tritium release behavior. In this study, the amount of surface water released from Li 4 SiO 4 is quantified by the experiment. In addition, the tritium release behavior from Li 4 SiO 4 are estimated based on the tritium release model using parameters obtained in our studies under conditions of commercial reactor operation and ITER test blanket module operation. The effect of the surface water on tritium release behavior is discussed from the obtained results. Moreover, the tritium inventory of Li 4 SiO 4 is discussed based on calculation under the unsteady state condition. Further, the effects of grain size and temperature on distribution of tritium inventory under the steady state condition are evaluated, and the optimal grain size is discussed from the view point of tritium release from Li 4 SiO 4 .

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