Title :
Insulation interlaminar shear strength testing with compression and irradiation
Author :
McManamy, T.J. ; Brasier, J.E. ; Snook, P.
Author_Institution :
Oak Ridge Nat. Lab., TN, USA
Abstract :
The Compact Ignition Tokamak (CIT) project identified the need for research and development for the insulation to be used in the toroidal field coils. The requirements included tolerance to a combination of high compression (380 MPa) and shear (93-MPa shear stress) and a high radiation does (approximately 1010 rad). The materials included various combinations of epoxy, polyimide, E-glass, S-glass, and T-glass in the form of a three-dimensional (3-D) weave. The data before irradiation for smaller sample configurations developed for irradiation tests were similar to those for the larger samples, but approximately 10% lower. Limited fatigue testing was also performed by cycling the shear load. No reduction in shear strength was found after 50000 cycles at 90% of the failure stress. Because of space limitations, only three materials were chosen for irradiation: two polyimide systems and one epoxy system. The shear strength with compression before and after irradiation at the lower dose was determined
Keywords :
Tokamak devices; fusion reactor materials; fusion reactor theory and design; plasma toroidal confinement; Compact Ignition Tokamak; E-glass; S-glass; T-glass; compression; epoxy; fatigue testing; insulation interlaminar shear strength testing; irradiation; polyimide; radiation does; shear load; three-dimensional weave; toroidal field coils; Glass; Ignition; Insulation testing; Laboratories; Materials testing; Plasma chemistry; Polyimides; Sheet materials; Space technology; Stress;
Conference_Titel :
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location :
Knoxville, TN
DOI :
10.1109/FUSION.1989.102235
