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研究了两种新锆合金经不同中间退火组合后的力学性能和高压釜内含锂水中的耐蚀性能.结果表明:采用低温中间退火组合的样品具有更好的机械性能;对高Nb合金来说也有益于耐蚀性能的提高,低Nb合金在耐蚀性能不随中间退火组合温度的变化而改变.文中从第二相的角度对引起性能变化的原因进行了分析.

参考文献

[1] Saol G P;A M Garde;E R Bradley.In reactor ccorrosion performance of Zirlo and Zircaloy-4Zirconium in the Nuclear Industry:Tenth International SymposiumASTM STP 1245[J].American Society for Testing and Materials,1994:724-744.
[2] Mardon J P et al.Development of New Zirocnium Alloys for PWR Fuel Rod Cladding[Z].ANS West Palm BeachApril,1994.
[3] Nikulina A V;Rbradley;GP-SabolEds.Zirconium Alloy E635 as a Material for Fuel Rod Cladding and other components of VVER and other components of VVER and RBNK Cores Zirconiun in the Nuclear Industry Eleventh Intemational Symposium ASTM STP 1295[J].American Society for Testing and Materials,1996:785-804.
[4] 李中奎,刘建章,朱梅生.合金元素对Zr-Sn-Fe-Cr-Nb合金性能的影响[J].稀有金属材料与工程,1996(05):43-48.
[5] 朱梅生 .热处理对合金腐蚀性能的研究[J].稀有金属材料与工程,1997,26(04)
[6] 李中奎,刘建章,李佩志.新锆合金在两种不同介质中的耐蚀行为[J].稀有金属材料与工程,1999(02):101-104.
[7] Garzarolli F;et al".Influence of various additions to water on Zircaloy-4 corrosion in Autoclave Tests at 350℃ in Proceeding of IAEA Technical commitee Meeting on Fundametal Aspects of corrosion of Zirconium-base Alloys in water Reactor Environments IAEA[J].Vienna,1990
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