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Zirconium Alloys for Supercritical Water Reactor Applications: Challenges and Possibilities

机译:用于超临界水反应堆的锆合金:挑战和可能性

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A preliminary assessment reveals the possibilities andchallenges of using zirconium alloys in the SCWR. Inparticular, in comparison with other alloys beingconsidered for the SCWR, the Zr alloys showed highercorrosion rates than austenitic alloys, and somewhat lowercorrosion rates than ferritic-martensitic alloys, at least upto the times that these steels have been tested insupercritical water (about 30 days). Issues related tomechanical properties and hydrogen uptake will still haveto be resolved.
机译:初步评估揭示了可能性和 SCWR中使用锆合金的挑战。在 特别是与其他合金相比 考虑到SCWR,Zr合金显示出更高的 腐蚀速率比奥氏体合金低一些 腐蚀速率至少比铁素体-马氏体合金高 到这些钢已经过测试的时间 超临界水(约30天)。有关的问题 机械性能和氢吸收仍将 有待解决。

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