论文摘要
A major dilemma faced in the nuclear industry is repair of stainless steel reactor components that have been exposed to neutron irradiation. When conventional fusion welding is used for repair, intergranular cracks develop in the heat-affected zone（HAZ）. Friction stir processing（FSP）, which operates at much lower peak temperatures than fusion welding, was studied as a crack repair method for irradiated 304 L stainless steel. A numerical simulation of the FSP process in 304 L was developed to predict temperatures and recrystallized grain size in the stir zone. The model employed an Eulerian finite element approach,where flow stresses for a large range of strain rates and temperatures inherent in FSP were used as input. Temperature predictions in three locations near the stir zone were accurate to within 4%, while prediction of welding power was accurate to within 5% of experimental measurements. The predicted recrystallized grain sizes ranged from 7.6 to 10.6 μm, while the experimentally measured grains sizes in the same locations ranged from 6.0 to 7.6 μm. The maximum error in predicted recrystallized grain size was about 39%, but the associated stir zone hardness from the predicted grain sizes was only different from the experiment by about 10%.
论文目录
文章来源
类型: 期刊论文
作者: M.P.Miles,T.W.Nelson,C.Gunter,F.C.Liu,L.Fourment,T.Mathis
来源: Journal of Materials Science & Technology 2019年04期
年度: 2019
分类: 工程科技Ⅰ辑,工程科技Ⅱ辑
专业: 金属学及金属工艺,核科学技术
单位: Manufacturing Engineering Department,Brigham Young University,Centre de Mise en Forme des Materiaux,Mines ParisTech
基金: supported by the National Science Foundation grant CMMI-1405508
分类号: TL35;TG453.9
页码: 491-498
总页数: 8
文件大小: 1635K
下载量: 9