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Fusion Engineering and Design 81 (2006) 461467 An overview of dual coolant Pb17Li breeder first wall and blanket

Summary: Fusion Engineering and Design 81 (2006) 461­467
An overview of dual coolant Pb­17Li breeder first wall and blanket
concept development for the US ITER-TBM design
C.P.C. Wonga,, S. Malangb, M. Sawanc, M. Dagherd, S. Smolentsevd, B. Merrille,
M. Youssefd, S. Reyesf, D.K. Szeg, N.B. Morleyd, S. Sharafatd, P. Calderonid,
G. Sviatoslavskyc, R. Kurtzh, P. Fogartyi, S. Zinklei, M. Abdoud
a General Atomics, P.O. Box 85608, San Diego, CA 92186-5608, USA
b Fusion Nuclear Technology Consulting, Linkenheim, Germany
c University of Wisconsin, Madison, WI, USA
d University of California, Los Angeles, CA, USA
e INEEL, Idaho Falls, ID, USA
f Lawrence Livermore National Laboratory, Livermore, CA, USA
g University of California, San Diego, CA, USA
h Pacific Northwest Laboratory, Richland, WA, USA
i Oak Ridge National Laboratory, Oak Ridge, TN, USA
Received 25 February 2005; received in revised form 31 March 2005; accepted 2 May 2005
An attractive blanket concept for the fusion reactor is the dual coolant Pb­17Li 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 Pb­17Li is circulated for power conversion and for tritium breeding. A SiCf/SiC composite insert is used


Source: Abdou, Mohamed - Fusion Science and Technology Center, University of California at Los Angeles


Collections: Plasma Physics and Fusion