Uses of zirconium alloys in fusion applications

Calculations are presented showing the generation of hydrogen and helium ga s and cascade damage (expressed in displacements per atom) for zirconium al loys. After a typical first wall exposure of five years, the hydrogen conte nt of a Zr-alloy increases by a factor of similar to1.5 over that initially present, suggesting that hydrogen embrittlement is unlikely to be a life-l imiting factor. Structural analyses of a typical first wall using zirconium alloy indicate that Zr-alloys may have satisfactory properties, and should be reconsidered for use in fusion applications. (C) 2000 UKAEA FUSION. Pub lished by Elsevier Science B.V. All rights reserved.