Measurement system for in-pile tritium monitoring from Li2TiO3 ceramics at WWRK reactor

A 220-day irradiation of Li2TiO3 ceramics with 96% enrichment of isotope 6Li was carried out at WWRK reactor. One of the study goals was to examine tritium release behavior during Li burn-up. To achieve this goal three types of ceramics samples were examined simultaneously using a system for in-pile...

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Bibliographic Details
Published in:Journal of nuclear materials 2007-08, Vol.367-370, p.1028-1032
Main Authors: CHIKHRAY, Y, SHESTAKOV, V, KULSARTOV, T, TAZHIBAYEVA, I, KAWAMURA, H, KUYKABAEVA, A
Format: Article
Language:English
Subjects:
Applied sciences
Controled nuclear fusion plants
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Installations for energy generation and conversion: thermal and electrical energy
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Summary:A 220-day irradiation of Li2TiO3 ceramics with 96% enrichment of isotope 6Li was carried out at WWRK reactor. One of the study goals was to examine tritium release behavior during Li burn-up. To achieve this goal three types of ceramics samples were examined simultaneously using a system for in-pile tritium monitoring: one (pebbles) - under constant temperature of 650 deg C, and two (pebbles and pellets) - within temperature change ranges from 500 to 900 deg C. Flows of tritium release from ceramics during the various reactor campaigns, as well as tritium generation rates for each ampoule are presented in the paper. The main result is justification of burn-up in 6Li reaching up to 20% of Li2TiO3 ceramics.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2007.03.184