Title :
ITER breeding blanket design
Author :
Gohar, Y. ; Billone, M. ; Cardella, A. ; Dänner, W. ; Ioki, K. ; Kuroda, T. ; Lousteau, D. ; Lorenzetto, P. ; Majumdar, S. ; Mattas, R. ; Mohri, K. ; Raffray, R. ; Strebkov, Y. ; Takatsu, H. ; Zolti, E.
Author_Institution :
ITER Joint Central Team, Garching, Germany
fDate :
30 Sep-5 Oct 1995
Abstract :
A breeding blanket design has been developed for ITER to provide the necessary tritium fuel to achieve the technical objectives of the Enhanced Performance Phase. It uses a ceramic breeder and water coolant for compatibility with the ITER machine design of the Basic Performance Phase. Lithium zirconate and lithium oxide are the selected ceramic breeders based on the current data base. Enriched lithium and beryllium neutron multiplier are used for both breeders. Both forms of beryllium material, blocks and pebbles are used at different blanket locations based on thermo-mechanical considerations and beryllium thickness requirements. Type 316LN austenitic steel is used as structural material similar to the shielding blanket. Design issues and required R&D data are identified during the development of the design
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor design; fusion reactors; Be; Enhanced Performance Phase; H2O; ITER; Li; Li2O; Li2ZrO3; breeding blanket design; ceramic breeder; structural material; type 316LN austenitic steel; water coolant; Conducting materials; Fabrication; Lithium; Moisture; Neutrons; Plasmas; Research and development; Temperature sensors; Thermal conductivity; Thermal stresses;
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
DOI :
10.1109/FUSION.1995.534253
