期刊
PROGRESS IN NUCLEAR ENERGY
卷 48, 期 4, 页码 325-359出版社
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.pnucene.2005.09.011
关键词
zircaloys; texture; mechanical anisotropy; formability; plasticity; twinning; CODF
This paper is a review of the texture development in zirconium alloys (in the form of thick walled tube reduced extrusion or TREX, thin-walled tubing and sheets) of importance to light and heavy water nuclear reactor technology along with the resultant anisotropic mechanical properties. Quantitative characterization of texture and mechanical anisotropy are emphasized leading to procedures useful to fabricators in optimizing textures for good formability as well as for acceptable in-service performance. A brief history of the development of zirconium alloys is presented followed by texture development and characterization. Mechanical anisotropy is discussed in terms of transverse contractile strain ratios from which the formability (B parameter) is derived. Results on the effect of annealing temperature as well as test temperature on anisotropy parameters are presented. The review concludes with a brief summary of texture effects on creep, stress corrosion cracking and hydride formation. Recent advances in fuel cladding bring out the challenges in characterizing the texture and anisotropy due to Nb additions and microstructural gradients in the new Zircaloys(TM), (1) such as Zirlo(TM),(2), Duplex(TM), (3) and Triclad (TM). (4). (C) 2005 Elsevier Ltd. All rights reserved.
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