Title of article
Uses of zirconium alloys in fusion applications
Author/Authors
Forty، نويسنده , , C.B.A. and Karditsas، نويسنده , , P.J.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2000
Pages
4
From page
607
To page
610
Abstract
Calculations are presented showing the generation of hydrogen and helium gas and cascade damage (expressed in displacements per atom) for zirconium alloys. After a typical first wall exposure of five years, the hydrogen content of a Zr-alloy increases by a factor of ∼1.5 over that initially present, suggesting that hydrogen embrittlement is unlikely to be a life-limiting 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.
Journal title
Journal of Nuclear Materials
Serial Year
2000
Journal title
Journal of Nuclear Materials
Record number
1347230
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