• 主题
高级搜索  >
历史搜索 清空历史
首页> 外文期刊>Quantum Beam Science >Through-Thickness Microstructure Characterization in a Centrifugally Cast Austenitic Stainless Steel Nuclear Reactor Primary Loop Pipe Using Time-of-Flight Neutron Diffraction
【24h】

Through-Thickness Microstructure Characterization in a Centrifugally Cast Austenitic Stainless Steel Nuclear Reactor Primary Loop Pipe Using Time-of-Flight Neutron Diffraction

机译：使用飞行时间中子衍射在离心铸造奥氏体不锈钢核反应堆初级回路管中的贯穿厚度微观结构

获取原文
           
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

The US code of Federal Regulations mandates regular inspection of centrifugally cast austenitic stainless steel pipe, commonly used in primary cooling loops in light-water nuclear power plants. These pipes typically have a wall thickness of ~8 cm. Unfortunately, inspection using conventional ultrasonic techniques is not reliable as the microstructure strongly attenuates ultrasonic waves. Work is ongoing to simulate the behavior of acoustic waves in this microstructure and ultimately develop an acoustic inspection method for reactor inspections. In order to account for elastic anisotropy in the material, the texture in the steel was measured as a function of radial distance though the pipe wall. Experiments were conducted on two 10 × 12.7 × 80 mm radial sections of a cast pipe using neutron diffraction scans of 2 mm slices using the HIPPO time-of-flight neutron diffractometer at the Los Alamos Neutron Science Center (LANSCE, Los Alamos, NM, USA). Strong textures dominated by a small number of austenite grains with their (100) direction aligned in the radial direction of the pipe were observed. ODF analysis indicated that up to 70% of the probed volume was occupied by just three single-grain orientations, consistent with grain sizes of almost 1 cm. Texture and phase fraction of both ferrite and austenite phases were measured along the length of the samples. These results will inform the development of a more robust diagnostic tool for regular inspection of this material.
机译：美国联邦法规守则要求定期检查离心铸造奥氏体不锈钢管，通常用于轻水核电厂的初级冷却环。这些管通常具有〜8cm的壁厚。遗憾的是，随着微观结构强衰减超声波的检查，使用传统的超声波技术的检测是不可靠的。工作正在进行中，以模拟这种微观结构中声波的行为，并最终开发用于反应堆检查的声学检查方法。为了考虑材料中的弹性各向异性，测量钢中的质地作为管壁径向距离的函数。使用中子衍射扫描的铸造管的径向截面进行实验，使用洛杉矶阿拉莫斯中子科学中心（Lansce，Los Alamos，NM，美国）。观察到由少量奥氏体晶粒主导的强烈纹理，其（100）方向在管道的径向方向上对齐。 ODF分析表明，高达70％的探测体积仅占三个单粒取向，含有近1厘米的晶粒尺寸。沿着样品的长度测量铁素体和奥氏体相的纹理和相位。这些结果将向开发更强大的诊断工具，用于定期检查该材料。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱：kefu@zhangqiaokeyan.com

京公网安备：11010802029741号 ICP备案号：京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有

  • 客服微信

  • 服务号