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Embrittlement and flow localization of reactor structural materials.

机译:反应堆结构材料的脆化和流动局部化。

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摘要

Type 300-series austenitic stainless steel has been widely used as structure materials in current light water reactors and continuing of interest in fusion systems and generation IV reactor designs. The flow localization process is characterized by a severe reduction in uniform elongation under tensile loading conditions following irradiation. Recent work shows that this process can be characterized by a critical stress: necking always occurs at the same value of true stress regardless of the level of irradiation hardening.; Microstructural analysis utilizing scanning electron microscopy (SEM) coupled with electron backscattering diffraction (EBSD) exhibits that for the materials tested at room temperature, there are extensive mechanical twinning bands, which could inhibit the mobility of dislocations thus, improve material's straining hardening and ductility. However, for the material tested at above 200°C, the twinning bands are completely absent. The critical twinning stress is highly dependent on the testing temperatures because of the temperature dependence of stacking fault energy. When the specimen is tested at room temperature, the critical stress is much larger than the critical twinning stress, so the mechanical twinning is activated at that point and fully developed until the onset of necking. However, when the specimen is tested at the elevated temperatures, even the critical stress is smaller than the critical twinning stress which makes the activation of mechanical twinning impossible. The mechanical twinning and dislocation-based planar slip are competing mechanism for the plastic deformation of 316L stainless steel. It is clear that strong textures at Brass and rotation Goss are considerably developed. Macro-texture investigation by XRD combining with the micro-texture examination using EBSD indicate that the underlying controlling mechanism for texture evolution is the dislocation-based planar slip instead of the formation of twinning bands as thought before.; Notch effects have been analyzed utilizing finite element method (FEM) and EBSD misorientation map for unirradiated and irradiated 316L stainless steel. The major issue of interest is the possibility that low ductility, often found following irradiation exposure, will translate into low notch toughness. The influence of irradiation exposure can also lead to flow localization problems with components with notches or stress concentrators.
机译:300系列奥氏体不锈钢已被广泛用作当前轻水反应堆的结构材料,并且在聚变系统和第四代反应堆设计中继续引起人们的兴趣。流动局部化过程的特征在于辐照后在拉伸载荷条件下均匀伸长率大大降低。最近的工作表明,该过程的特征可以是临界应力:颈缩总是以相同的真实应力值发生,而不管辐射硬化的程度如何。利用扫描电子显微镜(SEM)结合电子反向散射衍射(EBSD)进行的微结构分析表明,对于在室温下测试的材料,存在广泛的机械孪生带,可以抑制位错的迁移率,从而改善材料的应变硬化和延展性。但是,对于在200°C以上进行测试的材料,完全不存在孪生带。由于堆垛层错能量的温度依赖性,临界孪生应力高度依赖于测试温度。当样品在室温下测试时,临界应力比临界孪生应力大得多,因此机械孪生在该点被激活并充分发展直至出现颈缩。然而,当在高温下测试样品时,即使临界应力也小于临界孪生应力,这使得不可能激活机械孪生。基于机械孪晶和位错的平面滑移是316L不锈钢塑性变形的竞争机制。显然,黄铜和旋转高斯的坚固纹理已得到显着发展。通过XRD进行的宏观纹理研究以及使用EBSD进行的微观纹理检查表明,纹理演化的基本控制机制是基于位错的平面滑移,而不是以前所认为的孪生带的形成。已使用有限元方法(FEM)和EBSD取向错误图分析了未辐照和辐照316L不锈钢的缺口效应。感兴趣的主要问题是通常在辐照后发现的低延展性可能转化为低的缺口韧性。辐射暴露的影响还可能导致带有槽口或应力集中器的组件出现流局部化问题。

著录项

  • 作者

    Wu, Xianglin.;

  • 作者单位

    University of Illinois at Urbana-Champaign.;

  • 授予单位 University of Illinois at Urbana-Champaign.;
  • 学科 Engineering Nuclear.; Engineering Materials Science.
  • 学位 Ph.D.
  • 年度 2007
  • 页码 174 p.
  • 总页数 174
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;工程材料学;
  • 关键词

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