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The second LIBRETTO irradiation experiment with in-situ tritium release measurements on the eutectic alloy PB-17Li was performed in the High Flux Reactor (HFR) Petten. Static alloy samples were irradiated in closed capsules with different plenum volumes and cladding materials, with and without a permeation barrier, up to a Li burnup of 1.15%. Tritium release by permeation was measured in-situ. The main irradiation parameter was the material temperature. Temperature transients between 760 and 560 K were performed to study tritium release kinetics. Tritium residence times ranged from 1.4 to 40 hours for capsules with a permeation barrier. The aluminide permeation barrier increased the tritium residence times at 570 K by a factor of 4.5. No tritium release was observed at temperatures below 540 K. The post-irradiation neutron-radiograph images showed a volumetric increase of the alloy by gas bubbles, presumable helium formed under irradiation, of 2 to 13%, depending on the initial plenum volume.

Additional information

Authors: CONRAD R, JRC Petten (NL);DEBARBERIS L, JRC Petten (NL);COEN V, JRC Ispra (IT);FLAMENT T, CEA, Saclay (FR)
Bibliographic Reference: Paper presented: ICFRM-4, Kyoto (Japan), Dec. 4-8, 1989
Availability: Available from (1) as Paper EN 35040 ORA
Record Number: 199010050 / Last updated on: 1994-12-01
Original language: en
Available languages: en