Abstract

Analysis of the published to date results for hydrogen solubility in zirconium alloys—core structural materials of water-cooled nuclear reactors is presented. Data for hydrogen solubility in Russian domestic and foreign zirconium alloys are summarized.

中文翻译：

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锆合金中的氢溶解度

摘要

迄今为止，已发表的关于氢在锆合金中的溶解度的分析结果得到了分析，锆合金是水冷核反应堆的核心结构材料。总结了氢在俄罗斯国内和国外锆合金中的溶解度数据。