...
首页> 外文期刊>Journal of nuclear engineering and radiation science >GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization
【24h】

GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization

机译:GTAW焊接的Inconel 625合金燃料包层,用于加拿大SCWR:微观结构和机械性质表征

获取原文
获取原文并翻译 | 示例
   

获取外文期刊封面封底 >>

       

摘要

Inconel 625 is considered one of the candidate materials for reactor fuel cladding in the Canadian supercritical water reactor (SCWR) design. Gas tungsten arc welding (GTAW) is being evaluated as a joining technique for SCWR fuel cladding since this method is widely used to join components in the power and nuclear industry. During the GTAW process, the welding thermal cycle produces different types of microstructures in both the heat-affected zone (HAZ) and fusion zone (FZ) that affect the material's mechanical properties. A series of welding experiments at various weld conditions were performed using an automatic GTAW orbital process on Inconel 625 alloy tubing. Simple analytical heat conduction and grain growth models were developed to predict weld temperature profiles and metallurgical transformations. Weld characterization included mechanical tests, optical microscopy, scanning electron microscopy-energy dispersive spectroscopy (SEM-EDS) elemental analysis, and microhardness measurements. Weld microstructural characterization revealed that a characteristic dendritic structure was formed in the FZ, while the HAZ exhibited larger equiaxed grains than those found in the base material (BM). SEM-EDS analysis showed no distinct alloying element segregation in both the HAZ and FZ. Welds produced with heat inputs of about 3.00 J/mm(3) presented similar mechanical properties as those observed in the BM. In these welds, grain growth was homogenously minimized in the FZ. It is concluded that the effective welding heat input control can optimize the weld microstructure and the weld mechanical properties in Inconel 625 tubing used as Canadian SCWR reactor fuel cladding.
机译:Inconel 625被认为是加拿大超临界水反应堆(SCWR)设计中反应堆燃料包壳的候选材料之一。钨极气体保护焊(GTAW)被认为是超临界水堆燃料包壳的一种连接技术,因为这种方法在电力和核工业中被广泛用于连接部件。在GTAW过程中,焊接热循环在热影响区(HAZ)和熔合区(FZ)产生不同类型的微观结构,影响材料的机械性能。在Inconel 625合金管上,采用自动GTAW轨道工艺,在各种焊接条件下进行了一系列焊接试验。开发了简单的分析热传导和晶粒生长模型,用于预测焊接温度分布和冶金转变。焊缝表征包括机械试验、光学显微镜、扫描电子显微镜能量色散光谱(SEM-EDS)元素分析和显微硬度测量。焊缝微观结构表征表明,在FZ中形成了特征性的树枝状结构,而HAZ显示出比母材(BM)中更大的等轴晶粒。SEM-EDS分析表明,HAZ和FZ中没有明显的合金元素偏析。热输入约为3.00 J/mm(3)的焊缝呈现出与BM中观察到的类似的机械性能。在这些焊缝中,FZ中的晶粒生长均匀地最小化。结果表明,有效的焊接热输入控制可以优化加拿大SCWR反应堆燃料包壳用Inconel 625管子的焊接组织和焊接力学性能。

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