Irradiation Creep of Zr-Alloys

被引:6
|
作者
Griffiths, M. [1 ]
Bickel, G. A. [1 ]
DeAbreu, R. [1 ]
Li, W. [1 ]
机构
[1] Canadian Nucl Labs, Chalk River, ON, Canada
关键词
Stainless steel; Thermal aging; Mechanical testing; Microstructure; Finite element method; ZR-2.5NB PRESSURE TUBES; DEFORMATION;
D O I
10.1007/978-3-319-51097-2_13
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Irradiation creep of Zr-alloy nuclear reactor core components affects the reactor performance and also limits the reactor life in cases where those components cannot easily be replaced. For Zr-2.5Nb pressure tubing irradiation creep has been extensively studied for a range of temperatures, between 250 and 350 degrees C, and dose rates, between 1 x 10(16) and 2 x 10(18) n m(-2) s(-1) (E > 1 meV), using data from various materials test reactors and power reactors. These studies have shown that irradiation creep is controlled by a complex combination of slip and diffusional mass transport (often referred to as irradiation growth in the absence of stress). Irradiation creep is dependent on the crystallographic texture, the dislocation structure, and the grain structure; the importance of each being a function of irradiation temperature and displacement damage rate. Data will be presented, together with mechanistic modelling, to show what factors affect creep under different irradiation conditions.
引用
收藏
页码:165 / 182
页数:18
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