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首页> 外文会议>Material Degradation and Related Managerial Issues at Nuclear Power Plants >STATUS REPORT ON MATERIAL DEGRADATION AT PAKS NPP
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STATUS REPORT ON MATERIAL DEGRADATION AT PAKS NPP

机译：PAPS NPP材料降解状态报告

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This paper describes the recent ageing related problems include steam generator tube degradation and deformation of CRDM (Control Rod Drive Mechanism) sleeve and liner at Paks NPP. Outer stress corrosion cracking (ODSCC) of austenitic stainless steel (08Ch18N10T) tubing in steam generators (SG) of Paks NPP caused lot of indication on the tubes. Macroscopic and microscopic examination, scanning electron microscopic examination, X-ray diffraction analysis, tensile test, chemical analysis have been carried out to investigate secondary oxide layers and tube materials on steam generator tubes pulled from four Units of Paks NPP. Anomalous outlet temperatures and decreased coolant flow rates were discovered in the core of Unit 1-2-3 at Paks NPP after steam generators decontamination. Comprehensive studies have been performed on the heat exchanger tubes originating from different steam generators (SGs) of the Paks NPP. In 2002-2003 deformation of sleeve and liner of the nozzle were observed on four CRDM (Control Rod Drive Mechanism). The defective nozzles were repaired and their liners and sleeves were replaced.
机译：本文介绍了最近与老化相关的问题，包括Paks NPP的蒸汽发生器管退化以及CRDM（控制杆驱动机构）套筒和衬套的变形。 Paks NPP蒸汽发生器（SG）中奥氏体不锈钢（08Ch18N10T）管的外应力腐蚀开裂（ODSCC）引起了许多指示。进行了宏观和微观检查，扫描电子显微镜检查，X射线衍射分析，拉伸试验，化学分析，以研究从四个Paks NPP机组上抽出的蒸汽发生器管道上的二次氧化物层和管道材料。蒸汽发生器去污后，在Paks NPP的1-2-3号机组核心发现异常的出口温度和降低的冷却剂流量。对源自Paks NPP的不同蒸汽发生器（SGs）的换热管进行了全面的研究。在2002-2003年间，在四个CRDM（控制杆驱动机构）上观察到喷嘴的套筒和衬套变形。维修了有故障的喷嘴，并更换了衬管和套筒。

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