Title :
Neutronics Features of a Dual Coolant Lithium Lead Test Blanket Module for ITER
Author :
Sawan, M.E. ; Youssef, M.Z.
Author_Institution :
Wisconsin Univ., Madison, WI
Abstract :
Neutronics analysis was performed for a dual coolant lithium lead blanket module to be tested in ITER. The total radial depth of the TBM is 41.3 cm followed by a 30 cm thick inlet/outlet piping zone. The calculated local tritium breeding ratio in the DCLL TBM is 0.741. The annual tritium production in the TBM is 2.4 g. The total nuclear heating in the TBM is 0.982 MW. The total thermal power to be removed from the TBM is 1.357 MW
Keywords :
coolants; fusion reactor blankets; fusion reactor ignition; fusion reactor theory; tritium handling; 0.982 MW; 1.357 MW; DCLL TBM; ITER; dual coolant lithium lead test blanket module; inlet piping zone; neutronics analysis; nuclear heating; outlet piping zone; radial depth; thermal power; tritium breeding; tritium production; Assembly; Coolants; Heating; Helium; Lithium; Performance analysis; Performance evaluation; Plugs; Silicon carbide; Testing; ITER; dual coolant lithium lead; neutronics; nuclear heating; test blanket module;
Conference_Titel :
Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
Conference_Location :
Knoxville, TN
Print_ISBN :
0-4244-0150-X
Electronic_ISBN :
0-4244-0150-X
DOI :
10.1109/FUSION.2005.252905
