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A REVIEW ON THE ODSCC OF STEAM GENERATOR TUBES IN KOREAN NPPS

机译:韩国NPPS蒸汽发生器管的ODSCC综述

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摘要

The ODSCC detected in the TSP position of Ulchin 3&4 SGs are typical ODSCC of Alloy 600MA tubes. The causative chemical environment is formed by concentration of impurities inside the occluded region formed by the tube surface, egg crate strips, and sludge deposit there. Most cracks are detected at or near the line contacts between the tube surface and the egg crate strips. The region of dense crack population, as defined as between 4th and 9th TSPs, and near the center of hot leg hemisphere plane, coincided well with the region of preferential sludge deposition as defined by thermal hydraulics calculation using SGAP computer code. The cracks developed homogeneously in a wide range of SGs, so that the number of cracks detected each outage increased very rapidly since the first detection in the 8th refueling outage. The root cause assessment focused on investigation of the difference in microstructure and manufacturing residual stress in order to reveal the cause of different susceptibilities to ODSCC among identical six units. The manufacturing residual stress as measured by XRD on OD surface and by split tube method indicated that the high residual stress of Alloy 600MA tube played a critical role in developing ODSCC. The level of residual stress showed substantial variations among the six units depending on details of straightening and OD grinding processes. Youngwang 3&4 tubes are less susceptible to ODSCC than U3 and U4 tubes because semi-continuous coarse chromium carbides are formed along the grain boundary of Y3&4 tubes, while there are finer less continuous chromium carbides in U3 and U4. The different carbide morphology is caused by the difference in cooling rate after mill anneal. There is a possibility that high chromium content in the Y3&4 tubes, still within the allowable range of Alloy 600, has made some contribution to the improved resistance to ODSCC. It is anticipated that ODSCC in Y5&6 SGs will be retarded more considerably than U3 SGs since the manufacturing residual stress in Y5&6 tubes is substantially lower than in U3 tubes, while the microstructure is similar with each other.
机译:在Ulchin 3&4 SG的TSP位置检测到的ODSCC是600MA合金管的典型ODSCC。致病性化学环境是由管表面,卵条带条和污泥在此处形成的封闭区域内的杂质浓度所形成的。在管子表面和蛋箱条之间的线接触处或附近发现了大多数裂纹。裂纹密集区的区域(定义为第4至第9个TSP之间),靠近热腿半球平面的中心,与通过SGAP计算机代码进行热力水力计算确定的优先污泥沉积区域重合。裂纹在各种SG中均一地扩展,因此自第8次加油中断中首次检测到以来,每次中断检测到的裂纹数量都迅速增加。根本原因评估集中于调查微观结构和制造残余应力的差异,以揭示相同六个单元之间对ODSCC敏感性不同的原因。 X射线衍射(OD)表面和分流管法测量的制造残余应力表明,600MA合金管的高残余应力在开发ODSCC中起着关键作用。残余应力水平在六个单元之间显示出很大的差异,具体取决于矫直和OD磨削过程的细节。 Youngwang 3&4管比U3和U4管更不易受到ODSCC的影响,因为沿Y3&4管的晶界形成了半连续的粗碳化铬,而U3和U4中的连续铬碳化物较少。不同的碳化物形态是由轧机退火后冷却速度的差异引起的。 Y3&4管中的高铬含量可能仍在合金600的允许范围内,这可能有助于提高其对ODSCC的抵抗力。可以预料,Y5&6 SG中的ODSCC将比U3 SG受到更大的阻碍,因为Y5&6管中的制造残余应力显着低于U3管中的制造残余应力,而微观结构彼此相似。

著录项

  • 来源
    《Nuclear engineering and technology》 |2013年第4期|513-522|共10页
  • 作者单位

    Central Research Institute, Korea Hydro Nuclear Power 70 1312-gil Yuseong-Daero Yusung-Gu Daejeon, 305-343, Korea;

    Central Research Institute, Korea Hydro Nuclear Power 70 1312-gil Yuseong-Daero Yusung-Gu Daejeon, 305-343, Korea;

    Central Research Institute, Korea Hydro Nuclear Power 70 1312-gil Yuseong-Daero Yusung-Gu Daejeon, 305-343, Korea;

    Central Research Institute, Korea Hydro Nuclear Power 70 1312-gil Yuseong-Daero Yusung-Gu Daejeon, 305-343, Korea;

    Central Research Institute, Korea Hydro Nuclear Power 70 1312-gil Yuseong-Daero Yusung-Gu Daejeon, 305-343, Korea;

    Central Research Institute, Korea Hydro Nuclear Power 70 1312-gil Yuseong-Daero Yusung-Gu Daejeon, 305-343, Korea;

    Central Research Institute, Korea Hydro Nuclear Power 70 1312-gil Yuseong-Daero Yusung-Gu Daejeon, 305-343, Korea;

    Central Research Institute, Korea Hydro Nuclear Power 70 1312-gil Yuseong-Daero Yusung-Gu Daejeon, 305-343, Korea;

    Central Research Institute, Korea Hydro Nuclear Power 70 1312-gil Yuseong-Daero Yusung-Gu Daejeon, 305-343, Korea;

    Nuclear Gaterials Research Division, Korea Atomic Energy Research Institute Daeieon, 305-353, Korea;

    Nuclear Gaterials Research Division, Korea Atomic Energy Research Institute Daeieon, 305-353, Korea;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    SG; Tube; ODSCC; Microstructure; Residual Stress; Sludge; Alloy 600(HT)MA;

    机译:SG;管;ODSCC;微观结构残余应力;污泥;600(HT)MA合金;

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