ITER blanket designs

• Published in: Fusion engineering and design 1995-03, Vol.27, p.52-61
• Main Authors: Gohar, Y, Parker, R, Rebut, P.-H
• Format: Article
• Language: English
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/0920-3796(95)90117-5

The ITER first wall, blanket, and shield system is being designed to handle 1.5 ± 0.3 GW of fusion power and 3 MWa m −2 average neutron fluence. In the basic performance phase of ITER operation, the shielding blanket uses austenitic steel structural material and water coolant. The first wall is made of bimetallic structure, austenitic steel and copper alloy, coated with beryllium and it is protected by beryllium bumper limiters. The choice of copper first wall is dictated by the surface heat flux values anticipated during ITER operation. The water coolant is used at low pressure and low temperature. A breeding blanket has been designed to satisfy the technical objectives of the Enhanced Performance Phase of ITER operation for the Test Program. The breeding blanket design is geometrically similar to the shielding blanket design except it is a self-cooled liquid lithium system with vanadium structural material. Self-healing electrical insulator (aluminum nitride) is used to reduce the MHD pressure drop in the system. Reactor relevancy, low tritium inventory, low activation material, low decay heat, and a tritium self-sufficiency goal are the main features of the breeding blanket design.