核电站关键材料在微纳米尺度上的环境损伤行为研究------进展与趋势

韩恩厚

doi:10.3724/SP.J.1037.2011.00441

金属学报 >

2011 , Vol. 47 >Issue 7: 769 - 776

DOI: https://doi.org/10.3724/SP.J.1037.2011.00441

综述

核电站关键材料在微纳米尺度上的环境损伤行为研究------进展与趋势

韩恩厚

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1) 中国科学院金属研究所金属腐蚀与防护国家重点实验室, 沈阳110016
2) 中国科学院金属研究所辽宁省核电材料安全与评价技术重点实验室, 沈阳 110016

韩恩厚, 男, 1961出生, 研究员

收稿日期: 2011-07-12

网络出版日期: 2011-07-11

基金资助

国家重点基础研究发展计划项目2011CB610500和国家科技重大专项项目2011ZX06004-009资助

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RESEARCH TRENDS ON MICRO AND NANO--SCALE MATERIALS DEGRADATION IN NUCLEAR POWER PLANT

HAN En-Hou

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1) State Key Laboratory for Corrosion and Protection, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016
2) Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016

Received date: 2011-07-12

Online published: 2011-07-11

Supported by

Supported by National Basic Research Program of China (No.2011CB610500) and National Science and Technology Major Project (No.2011ZX06004-009)

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摘要

分析了核电站用关键金属材料的损伤行为的研究现状, 叙述了近期的主要进展: 腐蚀电化学动力学、晶界上的优先氧化及由此导致的晶界强度降低、材料内部特殊晶界改善耐腐蚀性能、尖锐的应力腐蚀裂纹形状、纳米尺度原子团簇的形成及其对性能的影响等. 在此基础上指出, 在高温高压水中工作的核电站关键材料的环境损伤的研究趋势和主要问题包括: 材料在高温高压水中的腐蚀电化学动力学, 特别是杂质离子对腐蚀微观过程的影响; 表面膜和材料表层在微纳米尺度上的微观结构、物理性质、力学性质、化学性质和表面膜的再钝化行为, 特别是离子在表面膜和材料表层的传输过程; 微纳米尺度上材料初始加工表层、水化学参数对应力腐蚀裂纹孕育的影响, 以及穿晶应力腐蚀开裂的机理; 材料微观损伤研究结果与工程应用的结合等. 研究这些材料的环境行为需要精确控制研究状态和环境条件, 因此, 发展先进的的核电环境模拟技术和研究手段是获得核电站准确损伤行为的关键.

关键词： 核电关键材料; 不锈钢; 镍基合金; 低合金钢; 锆合金; 腐蚀; 应力腐蚀开裂; 腐蚀疲劳; 流动加速腐蚀; 辐照损伤

本文引用格式

韩恩厚 . 核电站关键材料在微纳米尺度上的环境损伤行为研究------进展与趋势[J]. 金属学报, 2011 , 47(7) : 769 -776 . DOI: 10.3724/SP.J.1037.2011.00441

Abstract

The recent research status of materials degradation in nuclear power plant (NPP) has been analyzed. The main research progresses include: kinetics of corrosion electrochemistry in high temperature pressurised water, preferential intergranular oxidation and the degradation of grain boundary strength, special grain boundary optimized materials corrosion resistance, tight crack of stress corrosion cracking, nano-scale atom cluster formation and effects. The research trends and key problems have been proposed, such as kinetics of corrosion electrochemistry in high temperature high pressure water, especially the effect of contaminating species on micro-process of corrosion; characterization of microstructure, physical, chemical and mechanical properties of surface film and near-surface materials, repassivation behavior of passive film, especially ion diffusion micro-process in the surface film and near-surface materials; the effects of as-received surface and water chemistry on crack incubation and initiation; application of materials degradation mechanisms. In order to characterize the material environmental behavior, it is important to control the research and environment condition, and to develop new test methods in simulated NPP environment.

Key words： key material in nuclear power plant; stainless steel; nickel--based alloy; low alloy steel; zirconium alloy; corrosion; stress corrosion cracking; corrosion fatigue,; flow assisted corrosion; irradiation degradation

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