Tritium control in a helium cooled ceramic blanket

The Karlsruhe Nuclear Center is studying the conceptual design of an helium cooled, poloidal ceramic blanket with beryllium multiplier for NET. To maintain the tritium losses from the plant below 10 curie/d, a separate helium purge flow is required. In the case of a high pressure purge flow, tritium containment requires an oxidizing atmosphere in the purge flow region. The consequences of the resulting T20 partial pressure on Li20 are assessed in the paper. A purge flow at 1 bar does not require an oxidizing atmosphere