Published 1989 | Version v1
Report

Shielding design options for the TF magnets of ITER (International Thermonuclear Experimental Reactor)

  • 1. Univ. of Wisconsin, Madison (USA)

Description

Optimization studies were performed to design an efficient shield to protect the toroidal field (TF) magnets of the International Thermonuclear Experimental Reactor (ITER). Several options for the shield design were examined and many shielding materials have been evaluated. The pure SS/H2O shield does not satisfy the magnet radiation limits. When boron carbide, lead, or boron steel is incorporated in the shield, all design limits are met. The highest damage occurs at the midplane of the inner legs and at the top/bottom parts of the magnets due to the limited space for the shield. The safety factors associated with the different magnet responses were quantified. These factors account for the increase in damage due to the presence of the assembly gaps between the shield modules and the uncertainties in data, codes, and modeling. 6 refs., 1 fig., 4 tabs

Additional details

Publishing Information

Imprint Title
IEEE thirteenth symposium on fusion engineering. Proceedings: Volume 2
Imprint Pagination
785 p.
Journal Page Range
p. 1329-1332.
Report number
CONF-891007--Vol.2

Conference

Title
13. IEEE symposium on fusion engineering.
Dates
2-6 Oct 1989.
Place
Knoxville, TN (USA).