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Abstract

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);JRC ISPRA (IT);CEA, SACLAY (FR);DEBARBERIS L, JRC PETTEN (NL);JRC ISPRA (IT);CEA, SACLAY (FR);COEN V, JRC PETTEN (NL);JRC ISPRA (IT);CEA, SACLAY (FR);FLAMENT T JRC PETTEN (NL), JRC PETTEN (NL);JRC ISPRA (IT);CEA, SACLAY (FR);JRC ISPRA (IT), JRC PETTEN (NL);JRC ISPRA (IT);CEA, SACLAY (FR);CEA, SACLAY (FR), JRC PETTEN (NL);JRC ISPRA (IT);CEA, SACLAY (FR)
Bibliographic Reference: PAPER PRESENTED: ICFRM-4, KYOTO (JAPAN), DEC. 4-8, 1989 AVAILABLE FROM COMMISSION OF THE EUROPEAN COMMUNITIES, DG XIII-C-3, L-2920 LUXEMBOURG AS PAPER EN 35040 ORA
Availability: Can be ordered online
Record Number: 1989128005600 / Last updated on: 1990-04-01
Category: PUBLICATION
Available languages: en