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

Volume

1

fYear

1995

fDate

30 Sep-5 Oct 1995

Firstpage

410

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;

fLanguage

English

Publisher

ieee

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

Type

conf

DOI

10.1109/FUSION.1995.534253

Filename

534253