Title of article
Specification of CuCrZr alloy properties after various thermo-mechanical treatments and design allowables including neutron irradiation effects
Author/Authors
Barabash، نويسنده , , V.R. and Kalinin، نويسنده , , G.M. and Fabritsiev، نويسنده , , S.A. and Zinkle، نويسنده , , S.J.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2011
Pages
4
From page
904
To page
907
Abstract
Precipitation hardened CuCrZr alloy is a promising heat sink and functional material for various applications in ITER, for example the first wall, blanket electrical attachment, divertor, and heating systems. Three types of thermo-mechanical treatment were identified as most promising for the various applications in ITER: solution annealing, cold working and ageing; solution annealing and ageing; solution annealing and ageing at non-optimal condition due to specific manufacturing processes for engineering-scale components. The available data for these three types of treatments were assessed and minimum tensile properties were determined based on recommendation of Structural Design Criteria for the ITER In-vessel Components. The available data for these heat treatments were analyzed for assessment of neutron irradiation effect. Using the definitions of the ITER Structural Design Criteria the design allowable stress intensity values are proposed for CuCrZr alloy after various heat treatments.
Journal title
Journal of Nuclear Materials
Serial Year
2011
Journal title
Journal of Nuclear Materials
Record number
1358686
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