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首页> 外文期刊>Metal Science and Heat Treatment >BEHAVIOR OF ATOMIC REACTOR ZIRCONIUM CLADDING FUEL ROD TUBES UNDER EXTREME OPERATING CONDITIONS
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BEHAVIOR OF ATOMIC REACTOR ZIRCONIUM CLADDING FUEL ROD TUBES UNDER EXTREME OPERATING CONDITIONS

机译:极端工作条件下原子反应堆包覆锆棒材的行为

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摘要

The effect of zirconium alloy strength on stress corrosion cracking for cladding tubes prepared from these materials is studied. Structure-phase transformations and the nature of failure during high-temperature oxidation, i.e. simulation of critical situations with loss of heat carrier (LOCA) for zirconium cladding tubes, are studied. Areas are analyzed for improving zirconium cladding tubes for fuel rods intended for a new generation of heat generation systems.
机译:研究了锆合金强度对由这些材料制成的覆层管应力腐蚀开裂的影响。研究了结构相变和高温氧化过程中的破坏性质,即模拟了锆熔覆管在热载流失(LOCA)时的临界情况。分析了用于改进用于新一代生热系统的燃料棒的锆包层管的区域。

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