Grid-to-rod flow-induced impact study for PWR fuel in reactor. (August 2016)

• Record Type: Journal Article
• Authors: Jiang, Hao; Qu, Jun; Lu, Roger Y.; Wang, Jy-An John
• Is Part Of: Progress in nuclear energy. Volume 91(2016:Aug.)
• Page Start: 355
• Page End: 361
• Publication Date: 2016-08
• Subjects: PWR -- Flow-induced impact -- Grid-to-rod dynamic contact; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 333.7924
• DOI: 10.1016/j.pnucene.2016.06.003
• Languages: English
• ISSNs: 0149-1970

Abstract

Abstract: Dynamic contact impact from hydraulic flow-induced fuel assembly vibration is the source for grid-to-rod fretting in a pressurized water nuclear reactor (PWR). To support grid-to-rod fretting wear mitigation research, finite element analysis (FEA) was used to evaluate the hydraulic flow-induced impact intensity between the fuel rods and the spacer grids. Three-dimensional FEA models, with detailed geometries of the dimple and spring of the actual spacer grids along with fuel rods, were developed for flow impact simulation. The grid-to-rod dynamic impact simulation provided insights of the contact phenomena at grid-rod interface. It is an essential and effective way to evaluate contact forces and provide guidance for simulative bench fretting-impact tests. Highlights: To support grid-to-rod fretting wear research, the flow-induced impact between fuel rods and spacer grids in a pressurized water nuclear reactor (PWR) was studied. 3-D FEA models, with detailed geometries of the dimple and spring of the actual spacer grids along with fuel rods, were developed for flow impact simulation. The grid-to-rod dynamic impact simulation provided insights of the contact phenomena at grid-rod interface. It is an essential and effective way to evaluate contact forces and provide guidance for simulative bench fretting-impact tests.