核电关键结构材料应力腐蚀裂纹裂尖微观力学特性分析
首发时间:2015-11-20
摘要:奥氏体不锈钢和镍基合金因为具有较好的高温耐腐蚀性,被广泛应用在核电一回路结构材料中,而核电一回路结构材料的应力腐蚀开裂(SCC)是核电结构材料破坏和失效的主要形式之一。研究表明,SCC过程是一个氧化膜不断破裂和生成的连续过程。本文以氧化膜破裂理论为依据,根据实验得到的裂尖形貌特征,利用有限元分析方法对高温水环境下304L奥氏体不锈钢含氧化膜SCC裂纹尖端裂尖微观力学状态进行了初步分析,为精确预测核电一回路结构材料应力腐蚀开裂扩展速率奠定一定基础。
关键词: 机械强度 核电结构材料 奥氏体不锈钢 应力腐蚀开裂 应力应变 有限元
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Analysis on micro-mechanical state at SCC tip in nuclear key structure materials
Abstract:Austenitic stainless steels nickel-based alloys and are widely used in primary circuit structures in nuclear power plants because of their good corrosion resistance in high temperature water environment, and the stress corrosion cracking (SCC) in one of main failure in the key structure materials in nuclear power plants. It is shown that SCC is a continued process of dense oxide film rupture and reform. Based on Oxide film rupture model and the morphology feature obtained by an experiment, the micro-mechanical state at SCC tip with oxide film of 304L austenitic stainless steel in high temperature water environment is analyzed by finite element method, which provides a foundation to improve the quantitative predicated ability of SCC growth rate in used in primary circuit structures in nuclear power plants.
Keywords: mechanical strength nuclear key structure materials austenitic stainless steels stress corrosion cracking stress-strain FEM
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核电关键结构材料应力腐蚀裂纹裂尖微观力学特性分析
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