首页> 外文会议>International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors >DEVELOPMENT AND VALIDATION OF A NEW EXPERIMENTAL DEVICE FOR STUDIES OF IODINE STRESS CORROSION CRACKING OF ZIRCONIUM ALLOYS
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DEVELOPMENT AND VALIDATION OF A NEW EXPERIMENTAL DEVICE FOR STUDIES OF IODINE STRESS CORROSION CRACKING OF ZIRCONIUM ALLOYS

机译:锆合金碘胁迫腐蚀裂纹研究新实验装置的开发与验证

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Zirconium alloys are widely used in the nuclearindustry as cladding material due to their goodthermo-mechanical, chemical and neutronicproperties as well as an excellent general corrosionresistance in many environments. Nonetheless,Iodine-induced Stress Corrosion Cracking (ISCC)is an identified failure mechanism that can occurin nuclear fuel cladding as a result of PelletCladding Interaction (PCI) during incidental powertransients in the reactor. In this study a newexperimental device allowing studies of ISCCin a controlled chemical environment is presented.The experiments are performed in an environmentthat is free of contaminants. First results show thatthe time to rupture of the specimen is inverselyrelated to the iodine partial pressure. The lowesttested iodine partial pressure, 150 Pa, resultedin an ISCC crack. Post-Mortem microstructuralobservations provide evidence of iodine corrosionof Zircaloy-4.
机译:锆合金广泛用于核行业作为覆层材料由于他们的好处热机械,化学和中子属性以及出色的普通腐蚀许多环境中的抵抗力。尽管如此,碘诱导的应力腐蚀裂解(ISCC)是可以发生的识别的失败机制在核燃料包覆由于颗粒的结果偶然权力界定互动(PCI)反应器中的瞬态。在这项研究中是一个新的允许ISCC研究的实验装置在给予受控化学环境中。实验在环境中进行这是没有污染物的。第一个结果表明标本破裂的时间是成反比的与碘部分压力有关。最低的测试碘部分压力,150 pa,导致在ISCC裂缝中。后验尸微观结构观察结果提供了碘腐蚀的证据锆罗伊 - 4。

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