Title :
Nuclear aspects of a solid wall blanket based on advanced ferritic steel and re-circulating Flibe
Author_Institution :
Wisconsin Univ., Madison, WI, USA
Abstract :
Nuclear analysis was performed for a solid wall blanket concept that uses the nano-composited ferritic (NCF) steel alloy 12YWT as structural material with Pb as the neutron multiplier and Flibe (Li2BeF4) as the tritium breeder and coolant. With an enrichment of 40% 6Li the overall tritium breeding ratio is expected to be ∼1.16 and the blanket energy multiplication is 1.13. The peak structure dpa and helium production rates are 77.6 dpa/FPY and 955 He appm/FPY, respectively, implying a lifetime of ∼3 FPY. The NCF structure dominates the total activity and decay heat. The Mo content in the NCF needs to be reduced from 0.02% to <0.01% for the structure waste to qualify as low level class C waste.
Keywords :
beryllium compounds; fusion reactor blankets; lead; lithium compounds; nanocomposites; radioactive waste disposal; steel; tritium; tritium handling; Li2BeF4; Pb; T; blanket energy multiplication; decay heat; ferritic steel; helium production rates; low level class C waste; nanocomposited ferritic steel alloy; neutron multiplier; nuclear analysis; peak structure; recirculating Flibe; solid wall blanket; structural material; structure waste; tritium breeder; tritium breeding ratio; tritium coolant; Building materials; Coolants; Helium; Iron alloys; Neutrons; Performance analysis; Power conversion; Solids; Steel; Temperature;
Conference_Titel :
Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on
Print_ISBN :
0-7803-7908-X
DOI :
10.1109/FUSION.2003.1426603