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U.S. Department of Energy
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Convertible liquid metal blankets for ITER with Pb-17Li as breeding material

Conference ·
OSTI ID:196936
; ;  [1]
  1. Kernforschungszentrum Karlsruhe Postfach (Russian Federation); and others
A convertible blanket (CB) is proposed, where, without replacement of the blanket structure, a nonbreeding liquid metal is used during the Basic Performance Phase (BBP) and the eutectic Pb-17Li during the Enhanced Performance Phase (EPP). The design is based on austenitic steel as structural material and an average neutron wall load of 1 MW/m{sup 2} and uses either helium or water cooling. A characteristic feature of the concept is that the designs for both coolant options are very similar in many aspects: A stiff segment box is used which withstands high pressures and disruption forces - The First Wall (FW) is directly cooled by toroidal coolant ducts; two independent cooling circuits are used. The quasi-stagnant liquid metal inside the blanket box (pool-type arrangements) is cooled by an array of poloidal hairpin-type tubes connected to headers at the blanket top - A leak tolerant design is provided, i.e. each weld is allowed to leak without requiring the immediate shutdown of the fusion reactor and the blanket exchange - The Pb-17Li is slowly circulated through the blanket for tritium removal outside vacuum vessel.
OSTI ID:
196936
Report Number(s):
CONF-940664--
Country of Publication:
United States
Language:
English