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ITER BLANKET AND SHIELD STUDIES FOR HIGH ASPECT RATIO DESIGN OPTION* Y .Gohar, H. Attaya, M. Billone,C. Johnson,J. Kopasz, S.Majumdar, R. Mattas, and D.L. Smith
 

Summary: ITER BLANKET AND SHIELD STUDIES FOR HIGH ASPECT RATIO DESIGN OPTION*
Y .Gohar, H. Attaya, M. Billone,C. Johnson,J. Kopasz, S.Majumdar, R. Mattas, and D.L. Smith
Argonne National Laboratory, 9700 S.Cass Ave., Argonne, IL 60439 USA
D. Lousteau, B. Nelson, and D. Williamson
Oak Ridge National Laboratory, P.O. Box 2009, Oak Ridge, TN 37831 USA
A. Raffray, A. Badawi, A. Ying, and M. Abdou
Universityof California,LA, 6288 Boelter Hall, Los Angeles, CA 90024-1597 USA
L. El-Guebaly,M. Sawan, I. Sviatoslavsky,E. Mogahed, and G.Kulcinski
Universityof Wisconsin, 1500Johnson Drive, Madison, WI 537061687 USA
The attractivenessof the high aspect ratio design (HARD)
option for ITER has motivated a study to asseSs the blanket and
shield design performance for this configuration relative to the
ITER reference design. The blanket and shield have been
configuredto take an advantageof the HARD option. The layered
solidbreederblanket conceptwith water-coolant and steel-structure
and the water-steel shield have been used. The changes in the
neutron wall loading distribution,the mechanical design, the net
tritium breeding ratio, the total tritium inventory, and the nuclear
heating profilesare evaluated. The tradeoff between the net tritium
breeding ratio, and the fuel operating cost is analyzed. The

  

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

 

Collections: Plasma Physics and Fusion