NOVEL LOTUS LITHIUM-LEAD FUSION BLANKET CONCEPT
Institut de Génie Atomique, Ecole Polytechnique Fédérale de Lausanne
CH-1015 Lausanne, Switzerland
#Present Address: M.A.N.E.D., UCLA, Los Angeles, CA 90024, USA
A new lithium-lead blanket is studied on the basis of the following criteria: (i) having a tritium breeding rate of at least 1.1; (ii) having compact modules and (iii) considering the compatibility of structural materials with the primary zonal components. Low-activation ferritic steel is employed as the first wall. This element of the blanket is followed by two breeding zones of Li17Pb83 (natural lithium) and Li6, using respectively the reference vanadium-alloy and the ferritic steel for structural support. Graphite together with the vanadium-alloy fulfils the role of the reflector. A safer variant of the blanket concept, using (SiC) in the reflecting zone, is also studied in spite of its lower albedo with respect to graphite. A flexible experimental module is designed for tritium breeding measurements, foil activation and spectrum measurement purposes.
KEYWORDS: Lithium-lead, Blanket concept, Fusion blanket, tritium breeders, Structural materials, Blanket reflectors