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首页> 外文会议>STP 1467; International Symposium on Zirconium in the Nuclear Industry; 20040613-17; Stockholm(SE) >Thermal Creep of Irradiated Zircaloy Cladding
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Thermal Creep of Irradiated Zircaloy Cladding

机译：辐照锆合金熔覆层的热蠕变

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As part of an effort to investigate spent-fuel behavior during dry-cask storage, thermal creep tests are being performed with defueled Zircaloy-4 cladding segments from two pressurized water reactors - Surry at ≈36 GWd/MTU burnup and H. B. Robinson at ≈67 GWd/MTU burnup, with corresponding fast (E > 1 MeV) fluence levels of 7x10~(25) and 14x10~(25) n/m~2. The Surry rods are particularly relevant because they were stored in an inert-atmosphere (He) cask for 15 years. The Robinson rods were received after reactor discharge and pool storage. Commensurate with their high burnup, the Robinson cladding has significant waterside corrosion and hydrogen uptake. Test results to-date indicate good creep ductility for both claddings in the 360-400℃ and 160-250 MPa (hoop-stress) regime. Partial recovery of radiation hardening may have occurred during the long tests at 400℃, which led to improved creep ductility. Creep-rate sensitivity is significant for stress and even more so for temperature. The higher hydrogen content in the Robinson material appears to have no detrimental effect on creep behavior at the test temperature. One Robinson sample, which ruptured in the weld region at 205℃ during cooling from 400v under stress (190 MPa), precipitated all visible hydrides in the radial direction.
机译：为了研究干木桶储存期间的乏燃料行为，正在对来自两个压水堆的Zircaloy-4燃料覆盖层段进行加燃料热蠕变测试-Surry≈36 GWd / MTU燃耗和HB Robinson≈67 GWd / MTU燃耗，相应的快速（E> 1 MeV）通量水平为7x10〜（25）和14x10〜（25）n / m〜2。 Surry棒特别有用，因为它们在惰性气氛（He）桶中存放了15年。将罗宾逊棒放在反应堆卸料和储存池之后。与它们的高燃耗相称，鲁滨逊覆层具有明显的水边腐蚀和氢吸收。迄今为止的测试结果表明，在360-400℃和160-250 MPa（环向应力）条件下，两种覆层均具有良好的蠕变延展性。在400℃的长时间测试中，辐射硬化可能会部分恢复，从而改善了蠕变延展性。蠕变速率敏感性对于应力非常重要，对于温度则更为重要。罗宾逊材料中较高的氢含量似乎对测试温度下的蠕变行为没有不利影响。一个Robinson样品在应力（190 MPa）下从400v冷却时在205℃的焊接区域破裂，使所有可见的氢化物沿径向析出。

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