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This report reviews studies of the transport of hydrogen isotopes in the DEMO relevant water-cooled Pb-17Li blanket to be tested in NET as well as in a self-cooled blanket, which uses Pb-17Li or Flibe as a liquid breeder material and V or Fe as a first wall material. The time dependence of tritium inventory and permeation in these blankets and of deuterium and tritium recycling in the self-cooled blanket are presented and discussed.

Additional information

Authors: REITER F, JRC Ispra (IT)
Bibliographic Reference: EUR 12804 EN (1990) 31 pp., MF, ECU 4, blow-up copy ECU 5
Availability: (2)
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