Austenitic stainless steels and high strength copper alloys for fusion components

被引:74
作者
Rowcliffe, AF
Zinkle, SJ
Stubbins, JF
Edwards, DJ
Alexander, DJ
机构
[1] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
[2] Univ Illinois, Dept Nucl Engn, Urbana, IL 61801 USA
[3] Pacific NW Lab, Richland, WA 99352 USA
关键词
D O I
10.1016/S0022-3115(98)00333-X
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
An austenitic stainless steel (316LN), an oxide-dispersion-strengthened copper alloy (GlidCop A125), and a precipitation-hardened copper alloy (Cu-Cr-Zr) are the primary structural materials for the ITER first wall/blanket and divertor systems. While there is a long experience of operating 316LN stainless steel in nuclear environments, there is no prior experience with the copper alloys in neutron environments. The ITER first wall (FW) consists of a stainless steel shield with a copper alloy heat sink bonded by hot isostatic pressing (HIP). The introduction of bi-layer structural material represents a new materials engineering challenge; the behavior of the bi-layer is determined by the properties of the individual components and by the nature of the bond interface. The development of the radiation damage microstructure in both classes of materials is summarized and the effects of radiation on deformation and fracture behavior are considered. The initial data on the mechanical testing of bi-layers indicate that the effectiveness of GlidCop A125 as a FW heat sink material is compromised by its strongly anisotropic fracture toughness and poor resistance to crack growth in a direction parallel to the bi-layer interface. (C) 1998 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:183 / 192
页数:10
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