铬涂层对锆合金表面的保护作用

Q3 Materials Science Koroze a ochrana materialu Pub Date : 2017-12-20 DOI:10.1515/kom-2017-0021
A. Krausová, L. Tůma, M. Novak, L. Cvrček, J. Krejčí, J. Macák
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引用次数: 6

摘要

摘要核安全的日益提高,对核燃料寿命延长和燃尽的要求越来越高,都是基于锆合金性能的提高。保护涂层似乎是一种有前途的方法,以减少其化学反应性和增加抗氢化。本文采用原位阻抗谱法研究了标准Zr1Nb锆合金的薄铬涂层。在模拟WWER主冷却剂环境中,温度为280°C,压力为8 MPa。结果表明:在此条件下,镀铬Zr1Nb合金的氧化速度明显慢于未镀铬Zr1Nb合金。
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Chromium Coating as a Surface Protection of Zirconium Alloys
Abstract Increasing of nuclear safety, higher demands for longer nuclear fuel campaign and higher levels of burnout are based on improving the properties of zirconium alloys. Protective coatings appears to be a promising way to reduce their chemical reactivity and increase resistance to hydriding. In this work, a thin chromium coating applied to a standard Zr1Nb zirconium alloy was studied using in-situ impedance spectroscopy. Exposure was carried out at a temperature of 280 ° C and a pressure of 8 MPa in a simulated WWER primary coolant environment. The results show that the chromium-coated Zr1Nb alloy is under these conditions oxidized significantly slower than the non-coated alloy.
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来源期刊
Koroze a ochrana materialu
Koroze a ochrana materialu Materials Science-Materials Science (all)
CiteScore
3.00
自引率
0.00%
发文量
8
审稿时长
14 weeks
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