An overview of dual coolant Pb-17Li breeder first wall and blanket concept development for the US ITER-TBM design

February 1, 2006

Conference Paper

An overview of dual coolant Pb-17Li breeder first wall and blanket concept development for the US ITER-TBM design

Abstract

An attractive blanket concept for the fusion reactor is the dual coolant Pb-17Li liquid (DCLL) breeder design. Reduced activation ferritic steel (RAFS) is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled breeder Pb-17LI is circulated for power conversion and for tritium breeding. A SiCf/SiC composite insert is used as the magnetohydrodynamic (MHD) insulation to reduce the impact from the MHD pressure drop of the circulating Ph-17Li and as the thermal insulator to separate the high temperature Pb-17Li from the helium cooled RAFS structure.

Revised: April 18, 2006 | Published: February 1, 2006

Citation

Wong C., S. Malang, M. Sawan, M. Dagher, S. Smolentsev, B. Merrill, and M. Youssef, et al. 2006. An overview of dual coolant Pb-17Li breeder first wall and blanket concept development for the US ITER-TBM design. In 7th International Symposium on Fusion Nuclear Technology, edited by Shimizu, A.; Ando, T.; Akiba, M., 81, 461-467. Amsterdam:North-Holland. PNNL-SA-47041.