Out-of-pile tritium extraction from lithium silicate

Breitung, W.; Elbel, H.; Lebkücher, Josef; Schumacher, G.; Werle, H.

doi:10.1016/0022-3115(88)90299-1

Cited by 21 publications

(3 citation statements)

References 1 publication

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“…A higher cracking in the pebbles might be the reason for the easier release, which is dominated in lithium orthosilicate by desorption phenomena [6,7]. The performed out-of-pile experiments are useful for investigating the physical mechanisms of tritium release, but, as clearly observed in Ref.…”

Section: Tritium Releasementioning

confidence: 93%

Post-irradiation examinations of Li4SiO4 pebbles irradiated in the EXOTIC-8 experiment

Piazza

Erbe

Rolli

et al. 2004

Journal of Nuclear Materials

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In the EXOTIC-8 irradiation experiment in the High Flux Reactor (HFR) in Petten, lithium orthosilicate (OSi) pebbles with 50% 6 Li-content were irradiated with the aim at investigating the behaviour of breeder ceramics at DEMO relevant burn-up. Specifically, changes in the mechanical stability as well as in the tritium release properties (in-pile and out-of-pile) had to be studied. After the completion of the irradiation, lithium orthosilicate pebble samples were shipped to the Research Centre of Karlsruhe (FZK) for post-irradiation examinations. The pebbles irradiated up to about 11% 6 Li burn-up showed an increase in smaller cracks in the bulk and the presence of larger through-cracks, but the amount of fragments is quite small and the pebbles maintained a very good crush load. On the basis of these results, it can be concluded that the OSi pebbles can withstand high burn-up irradiation without an unduly high fragmentation.

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Section: Tritium Releasementioning

confidence: 93%

Post-irradiation examinations of Li4SiO4 pebbles irradiated in the EXOTIC-8 experiment

Piazza

Erbe

Rolli

et al. 2004

Journal of Nuclear Materials

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“…While resorption has been determined to be the rate-limiting step in tritium release [49,55,56], the details of the release process are still not well understood.…”

Section: Tritium Resorption From In Lithium Aluminate Over the Tempermentioning

confidence: 99%

Ceramic breeder materials: Status and needs

Johnson

Noda

Roux

1998

Journal of Nuclear Materials

100

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“…A recent investigation of the desorption of H2O from UAIO2 suggest that there are two types of desorption sites (i.e., activation energies), 25 and tritium release from 1145104 has been fit to a model using two desorption sites. 26 The effect that surface coverage has on the desorption activation energy can be understood by examining more closely the desorption process. In tritium release experiments, what is regarded as the desorption step really involves two processes: (l) a surface reaction between tritium, which has diffused to the surface as T + , and chemisorbed hydrogen to form surface bound HTO or HT and (2) desorption of the.…”

Section: ! 17mentioning

confidence: 99%