Abstract
A blanket concept with eutectic Li17Pb83 as liquid breeder, suited for tritium production in an experimental Tokamak power reactor is outlined and discussed. This design has been developed to satisfy the INTOR-Phase-I specifications, in particular: (i) modular arrangement of the blanket units inside the vacuum vessel; (ii) no use of the heat deposited for electricity production, (iii) a net tritium breeding of at least 60%. In this article the main results of the neutronics and thermohydraulics analysis are reviewed and the problems identified. Methods to keep liquid in the breeder during operation are proposed and discussed. The consequences of a coolant tube rupture in a breeder unit appears to be the most serious problem.
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