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Abstract

In the last few years, different types of engineering units have been investigated for tritium recovery from the liquid Pb-17Li breeding material of fusion reactors. In the light of recent tritium solubility and chemical physical data of this alloys, the past work has been revised, giving the range of the operating conditions for each unit in order to limit the tritium permeation to the water cooling system from the blanket and the blanket tritium inventory.

Additional information

Authors: PIERINI G, JRC - ISPRA ESTAB. (ITALY);UNIVERSITY OF CAGLIARI (ITALY);BARATTI R, JRC - ISPRA ESTAB. (ITALY);UNIVERSITY OF CAGLIARI (ITALY);VIOLA A JRC - ISPRA ESTAB. (ITALY), JRC - ISPRA ESTAB. (ITALY);UNIVERSITY OF CAGLIARI (ITALY);UNIVERSITY OF CAGLIARI (ITALY), JRC - ISPRA ESTAB. (ITALY);UNIVERSITY OF CAGLIARI (ITALY)
Bibliographic Reference: FUSION REACTOR BLANKET AND FUEL CYCLE TECHNOLOGY, TOKAI-MURA, IBARAKI (JAPAN), OCT. 27-29, 1986 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 32847 ORA
Availability: Can be ordered online
Record Number: 1989125071100 / Last updated on: 1987-12-01
Category: PUBLICATION
Available languages: en