首页> 外文会议>LWR fuel performance meeting/Top fuel/WRFPM 2010 >Critical Failure Strains for Incipient Crack Formation in the Oxide and Hydride Layers in the Outer Surface Region of Zircaloy Fuel Cladding Tubes
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Critical Failure Strains for Incipient Crack Formation in the Oxide and Hydride Layers in the Outer Surface Region of Zircaloy Fuel Cladding Tubes

机译:锆合金熔覆管外表面区域的氧化物和氢化物层中形成裂纹的临界破坏应变

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摘要

In order to elucidate the phenomena in the incipient crack formation and the failure process of fuel rods at power ramp, separate effect tests were made to obtain the critical strains for crack initiation of the oxide layer and the hydride layer, respectively. Data sets (AE signal, internal pressure, tube diameter, test temperature) were recorded at both room temperature and 290 ℃ during the pressurization of each specimen with the oxide and the hydride layers, and the morphologies of the cracks were also observed. Test results showed that the critical hoop strains for cracking of the oxide layer on the Zircaloy fuel cladding tubes were 0.21% at room temperature and 0.22%-0.24% at 290 ℃. At room temperature, hydride cracking started at a low strain level; however at 290℃, a relatively high critical strain of around 0.34% was detected. The scatter was qualitatively interpreted from the XRD analysis of the zirconium hydride layer, which showed mixed hydride compositions including brittle s-hydride as well as 5-hydride particles. It was found from the results of a series of tests on the combined effects with and without the oxide layer and with and without radial hydride formation that there were hardly any cracks in radial hydrides embedded in the tubes in the case without the oxide layer. The metallography observation results clearly depicted that the combined effects of the oxide cracking and the radial hydride formation generated an incipient crack, which would act as the trigger for delayed hydride cracking.
机译:为了阐明在功率斜坡处燃料棒的初期裂纹形成和失效过程中的现象,进行了单独的效果测试,分别获得了氧化层和氢化物层裂纹萌生的临界应变。在每个样品用氧化物和氢化物层加压的过程中,在室温和290℃下记录数据集(AE信号,内压,管径,测试温度),并观察到裂纹的形态。试验结果表明,Zircaloy燃料包壳管上的氧化层开裂的临界环向应变在室温下为0.21%,在290℃下为0.22%-0.24%。在室温下,氢化物开裂在低应变水平下开始。然而,在290℃时,检测到的相对较高的临界应变约为0.34%。从氢化锆层的XRD分析定性地解释了散射,该分析显示混合的氢化物成分包括脆性的s-氢化物和5-氢化物颗粒。从对具有和不具有氧化物层以及具有和不具有放射状氢化物的综合效果的一系列测试的结果中发现,在没有氧化物层的情况下,嵌入在管中的放射状氢化物几乎没有裂纹。金相观察结果清楚地表明,氧化物开裂和放射状氢化物形成的综合作用产生了初期裂纹,这将是延迟氢化物裂解的触发因素。

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  • 会议地点 Orlando FL(US)
  • 作者单位

    Nippon Nuclear Fuel Development Co., Ltd. 2163 Narita-cho, Oarai-machi, Higashi-Ibaraki-gun, Ibaraki-ken 311-1313, Japan;

    Nippon Nuclear Fuel Development Co., Ltd. 2163 Narita-cho, Oarai-machi, Higashi-Ibaraki-gun, Ibaraki-ken 311-1313, Japan;

    Nippon Nuclear Fuel Development Co., Ltd. 2163 Narita-cho, Oarai-machi, Higashi-Ibaraki-gun, Ibaraki-ken 311-1313, Japan;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 核燃料及其生产;
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