Grid-to-rod flow-induced impact study for PWR fuel in reactor

Journal Article · Fri Jun 10 00:00:00 EDT 2016 · Progress in Nuclear Energy

DOI:https://doi.org/10.1016/j.pnucene.2016.06.003· OSTI ID:1319179

Jiang, Hao  ^[1]; Qu, Jun ^[1]; Lu, Roger Y. ^[2]; Wang, Jy-An John ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology
2. Westinghouse Electric Company, Hopkins, SC (United States)

The source for grid-to-rod fretting in a pressurized water nuclear reactor (PWR) is the dynamic contact impact from hydraulic flow-induced fuel assembly vibration. In order 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. Finally, it is an essential and effective way to evaluate contact forces and provide guidance for simulative bench fretting-impact tests.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• Grant/Contract Number: AC05-00OR22725
• OSTI ID: 1319179
• Alternate ID(s): OSTI ID: 1341209
• Journal Information: Progress in Nuclear Energy, Vol. 91, Issue C; ISSN 0149-1970
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR
flow-induced impact
grid-to-rod dynamic contact