将Zr-4合金样品分别放在盛有350℃,0.1 mol/L的LiOH和KOH水溶液的高压釜中进行腐蚀,当2种样品的氧化膜厚度相同时,用二次离子质谱仪(SIMS)测量Li+,K+和OH在氧化膜剖面上的浓度分布,发现进入氧化膜的Li+比k+深而且记数强度高,同时在LiOH水溶液中腐蚀的样品,其氧化膜中OH-的强度也比在KOH水溶液中腐蚀的样品高,这表明OH-在氧化膜中的分布和扩散与其对应的阳离子有关.根据以上结果讨论了Zr-4合金在LiOH水溶液中耐腐蚀性能降低的原因.
参考文献
| [1] | Hillner E;Chirigos J N .The Effect of Lithium Hydroxide and Related Solution on the Corrosion Rate of Zircaloy in 680°F Water[R].Report W APD-TM-307, Pittsburgh: Westinghouse Electric Corporation,1962. |
| [2] | Ramasubramanian N;Precoanin N;Ling V C.Lithium Uptake and the Accelerated Corrosion of Zirconium Alloys[A].Philadelphia:American Society for Testing and Materials,1989:187-201. |
| [3] | 刘文庆,李强,周邦新.锆锡合金腐蚀转折机理的讨论[J].稀有金属材料与工程,2001(02):81-84. |
| [4] | Jeong Y H;Baek J H;Kim S J et al.Corrosion Characteristics and Oxide Microstructure of Zircaloy-4 in Aqueous Alkali Hydroxide Solutions[J].Journal of Nuclear Materials,1999,270:322-333. |
| [5] | Yong Hwan Jeong;Kyeong Ho Kim;Jong Hyuk Baek .Cation incorporation into zirconium oxide in LiOH, NaOH, and KOH solutions[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,1999(2):221-224. |
| [6] | Young Suk Kim;Sang Chul Kwon .Crystallization and degradation of zirconium oxide in various pH solutions[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,1999(s12):165-173. |
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