Surface inventory of tritium on Li2TiO3

Kawagoe, Takahiro; Nishikawa, Masabumi; Baba, Akira; Beloglazov, S.

doi:10.1016/s0022-3115(01)00586-4

Cited by 44 publications

(14 citation statements)

References 16 publications

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“…It has been reported that moisture concentration in the sweep gas affects the tritium recovery. 22,23) In the present experiment, the effect of moisture concentration on the tritium recovery behavior was negligible because the moisture concentration in sweep gas was constant at less than 0.1 ppm and the ratio of HT/(HT+HTO) was in the range of 97±2%. Therefore, the sweep gas flow rate in the range of 100 to 950 cm 3 /min affected very little the tritium recovery from Li 2 TiO 3 pebble bed in the steady state.…”

Section: Irradiation Test With Multi-layered Pebble-bed Mockupmentioning

confidence: 76%

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li₂TiO₃Pebble Bed in Japan

Tsuchiya¹,

Nakamichi²,

Nagao³

et al. 2001

Journal of Nuclear Science and Technology

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Lithium titanate (Li 2 TiO 3 ) is one of the most attractive tritium breeders for breeding blanket in fusion reactor from view points of low tritium inventory, high chemical stability and so on. The data on the performance of a blanket mockup with pebble bed under neutron irradiation is needed for the design of breeding blanket. To obtain such data, two kinds of the blanket in-pile mockups with Li 2 TiO 3 pebble bed were developed and the in-situ tritium recovery experiments were carried out in the Japan Materials Testing Reactor (JMTR). In these studies, effects of various parameters, i.e., irradiation temperature, sweep gas flow rate, etc., on the tritium recovery behavior from Li 2 TiO 3 pebble bed were evaluated. It was found that the tritium recovery (R) to tritium generation (G) ratio (R/G) increased with increasing the temperature of Li 2 TiO 3 pebble bed and was saturated when the temperature of Li 2 TiO 3 pebble bed at the outside edge exceeded 300 • C. Additionally, the sweep gas flow rate in the range of 100 to 900 cm 3 /min affected very little the tritium recovery from Li 2 TiO 3 pebble bed. A good prospect for the design of breeding blankets using Li 2 TiO 3 pebble bed was obtained from these results of in-situ experiments.

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Section: Irradiation Test With Multi-layered Pebble-bed Mockupmentioning

confidence: 76%

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li₂TiO₃Pebble Bed in Japan

Tsuchiya¹,

Nakamichi²,

Nagao³

et al. 2001

Journal of Nuclear Science and Technology

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“…In Eq. 11, the adsorption capacity of water vapor was reported elsewhere [17], and that for hydrogen gas molecule such as HT was assumed to be negligible in this work.…”

Section: Transport Model In Opened-poresmentioning

confidence: 99%

Development of the Tritium Transport Model for Pebbles of Li<sub>2</sub>TiO<sub>3</sub>

Kobayashi

Oya

2018

Plasma and Fusion Research

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Tritium transport code in Li 2 TiO 3 pebbles were developed in this study. In the simulation code, tritium transports in a grain, a closed-pore and an opened-pore were modeled and combined. The tritium transport in grain was modeled by the tritium diffusion, trapping/detrapping by defects, and the annihilation process of defects. The adsorption/desorption equilibrium of diffusing tritium gas molecule was modeled for the tritium transports in opened-pores. A vacant-core and shell model was used to model the tritium transport in closedpores. The results by simulation code suggested that the tritium trapping by closed-pores would result in the shift of tritium release toward higher temperature side as dissociation of tritium gas molecule in closed-pores requires higher activation energy.

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“…Lithium titanate (Li 2 TiO 3 ) is one of the candidates as the tritium breeding materials in D-T fusion reactors [1][2][3][4][5][6][7]. It is well known that in an operation of fusion reactors, irradiation defects in Li 2 TiO 3 will be produced by neutrons and recoil helium and tritium [8].…”

Section: Introductionmentioning

confidence: 99%

Correlation between release of deuterium and annihilation of irradiation defects produced by gamma-ray in Li2TiO3

Toda

Kobayashi

Fujishima

et al. 2013

Fusion Engineering and Design

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Surface inventory of tritium on Li2TiO3

Cited by 44 publications

References 16 publications

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li₂TiO₃Pebble Bed in Japan

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li₂TiO₃Pebble Bed in Japan

Development of the Tritium Transport Model for Pebbles of Li<sub>2</sub>TiO<sub>3</sub>

Correlation between release of deuterium and annihilation of irradiation defects produced by gamma-ray in Li2TiO3

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Surface inventory of tritium on Li2TiO3

Cited by 44 publications

References 16 publications

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li2TiO3Pebble Bed in Japan

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li2TiO3Pebble Bed in Japan

Development of the Tritium Transport Model for Pebbles of Li<sub>2</sub>TiO<sub>3</sub>

Correlation between release of deuterium and annihilation of irradiation defects produced by gamma-ray in Li2TiO3

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In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li₂TiO₃Pebble Bed in Japan

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li₂TiO₃Pebble Bed in Japan