首页> 外文会议>13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007 >ASSESSMENT AND DISPOSITION OF CREVICE CORROSION FLAWS IN ZIRCONIUM ALLOY PRESSURE TUBES IN OPERATING CANDU REACTORS - PERSPECTIVES OF REGULATORY STAFf
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ASSESSMENT AND DISPOSITION OF CREVICE CORROSION FLAWS IN ZIRCONIUM ALLOY PRESSURE TUBES IN OPERATING CANDU REACTORS - PERSPECTIVES OF REGULATORY STAFf

机译:作业坎都反应器中锆合金压力管内裂纹腐蚀痕迹的评估和处置-监管人员的观点。

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Crevice corrosion has been observed since the early operation of CANDU power reactors, on the inner surface of pressure tubes where fuel bundle bearing pads sit. Traditionally, crevice corrosion flaws (CCFs) were assessed as planar against delayed hydride cracking (DHC) growth. However, with reactor ageing and associated increasing levels of corrosion induced hydrogen (deuterium) uptake, assessing these flaws as planar posed significant operational problems. A new assessment strategy has been pursued in which confirmed crevice corrosion flaws are assessed volumetrically using a proposed lower bound root radius. The paper explains what areas have been explored and what considerations have been given when assessing the acceptability of licensee's proposed new assessment strategy. It also describes measures and restrictions imposed by the regulatory authority to account for the uncertainties associated with the methodology in order to maintain the confidence on the structural integrity of the concerned components.
机译:自从CANDU动力反应堆投入运行以来,就一直观察到缝隙腐蚀,在燃料束轴承垫所在的压力管内表面上。传统上,缝隙腐蚀缺陷(CCF)被评估为平面,以防止氢化物裂纹(DHC)的延迟生长。然而,随着反应器老化和相关的腐蚀诱导的氢(氘)吸收水平的增加,将这些缺陷评估为平面会带来严重的运行问题。一直在寻求一种新的评估策略,其中使用拟议的下限根半径对已确认的缝隙腐蚀缺陷进行体积评估。该文件解释了在评估被许可人提议的新评估策略的可接受性时已探索了哪些领域以及已考虑了哪些注意事项。它还描述了监管机构为解决与方法相关的不确定性而施加的措施和限制,以保持对相关组件的结构完整性的信心。

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