In situ tritium recovery behavior from Li2TiO3 pebble bed under neutron pulse operation

Tsuchiya, Kazuyoshi; Kikukawa, A.; Hoshino, Tsuyoshi; Nakamichi, Masaru; Yamada, H.; Yamaki, Daiju; Enoeda, Mikio; Ishitsuka, Etsuo; Kawamura, Hiroshi; Ito, Hiroto; Hayashi, K.

doi:10.1016/j.jnucmat.2004.04.238

Cited by 12 publications

(9 citation statements)

References 10 publications

(13 reference statements)

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“…The mockup is composed of a set of slabs: 16 mm thick F82H; 12 mm thick Li 2 TiO 3 ; and 200 mm thick beryllium, The tritium production rate from 6 Li was estimated by the experiment and calculation [7]. The calculation results agree well with the experimental data within 2 and 11% for the campaigns without and with the reflector, respectively.…”

Section: Randds On Blanket Neutronicsmentioning

confidence: 63%

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Overview of research and development activities on fusion nuclear technologies in Japan

Tanaka¹

2006

Fusion Engineering and Design

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Section: Randds On Blanket Neutronicsmentioning

confidence: 63%

“…Overall tritium release behavior under the pulsed operation is almost the same as that under continuous irradiation conditions [6]. These activities are planned to be expanded to in-pile partial mockup testing in fission reactors in advance of the testing in ITER.…”

Section: Randds On In-pile Blanket Performancementioning

confidence: 97%

Overview of research and development activities on fusion nuclear technologies in Japan

Tanaka¹

2006

Fusion Engineering and Design

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“…The presence of hydrogen isotopes was assumed as hydrogen isotopes will be used as a purge gas in the blanket for fast tritium recovery. Therefore, most of tritium will release as gas molecular form (HT) as reported in the in-pile tritium recovery experiment [18]. The solubility of tritium gas molecule in Li 2 TiO 3 was roughly reported in ref.…”

Section: Simulation Codementioning

confidence: 89%

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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“…The diameter of a lithium titanate pebble used for deuterium ion irradiation was 2 mm [4,5], and 18 pebbles were employed in the present experiment. These pebbles were heated at 973 K for 1 h in a vacuum before the deuterium ion irradiation.…”

Section: Methodsmentioning

confidence: 99%

Deuterium retention and desorption behavior of lithium titanate

Hino¹,

Sato²,

Yamauchi³

et al. 2008

Fusion Engineering and Design

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In situ tritium recovery behavior from Li2TiO3 pebble bed under neutron pulse operation

Cited by 12 publications

References 10 publications

Overview of research and development activities on fusion nuclear technologies in Japan

Overview of research and development activities on fusion nuclear technologies in Japan

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

Deuterium retention and desorption behavior of lithium titanate

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