ITER blanket and shield studies for high aspect ratio design option

Author

Gohar, Y. ; Attaya, H. ; Billone, M. ; Johnson, C. ; Kopasz, J. ; Majumdar, S. ; Mattas, R. ; Smith, D.L. ; Lousteau, D. ; Nelson, B. ; Williamson, D. ; Raffray, A. ; Badawi, A. ; Ying, A. ; Abdou, M. ; El-Guebaly, L. ; Sawan, M. ; Sviatoslavsky, I. ; Mog

Author_Institution

Argonne Nat. Lab., IL, USA

fYear

1991

fDate

30 Sep-3 Oct 1991

Firstpage

1131

Abstract

The impact of the HARD (high aspect ratio design) option on the blanket and shield performance as concluded from CDA (conceptual design activity) is examined. The neutron wall load distributions were calculated for the different operating modes of HARD. The average neutron wall load over the test ports is 30 to 70% higher than CDA, which increases the testing capability of ITER. The net tritium breeding capability of HARD was calculated based on the use of CDA blanket design. The net tritium breeding ratio is 8% less than CDA. However, the increased average neutron wall load over the test sections overrides the impact on the external tritium supply because of shorter operating time for the same neutron fluence. The shielding analysis of HARD suggested several modifications to meet the design limits of CDA. The total inboard thickness at midplane should be restored to 84 cm with the vacuum gap between the shield and the vacuum vessel reduced to 2 cm as in CDA, or 86 cm inboard thickness with the current gap thickness of 4 cm. In addition, it is necessary to extend the upper parts of the side modules to provide extra shielding for the upper divertor region

Keywords

fusion reactor materials; fusion reactor theory and design; neutron flux; shielding; CDA; HARD; ITER blanket; breeding ratio; conceptual design activity; design limits; high aspect ratio design; midplane; modifications; neutron fluence; neutron wall load distributions; operating modes; shield studies; side modules; test ports; test sections; testing capability; total inboard thickness; upper divertor region; upper parts; vacuum gap; vacuum vessel; Costs; Fuels; Heating; Laboratories; Magnetic flux; Neutrons; Performance analysis; Plasma sources; Solids; Testing;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on

Conference_Location

San Diego, CA

Print_ISBN

0-7803-0132-3

Type

conf

DOI

10.1109/FUSION.1991.218672

Filename

218672