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

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.
Authors:
ORCiD logo [1] ;  [1] ;  [2] ;  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology
  2. Westinghouse Electric Company, Hopkins, SC (United States)
Publication Date:
Grant/Contract Number:
AC05-00OR22725
Type:
Accepted Manuscript
Journal Name:
Progress in Nuclear Energy
Additional Journal Information:
Journal Volume: 91; Journal Issue: C; Journal ID: ISSN 0149-1970
Publisher:
Elsevier
Research Org:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR; flow-induced impact; grid-to-rod dynamic contact
OSTI Identifier:
1319179
Alternate Identifier(s):
OSTI ID: 1341209

Jiang, Hao, Qu, Jun, Lu, Roger Y., and Wang, Jy-An John. Grid-to-rod flow-induced impact study for PWR fuel in reactor. United States: N. p., Web. doi:10.1016/j.pnucene.2016.06.003.
Jiang, Hao, Qu, Jun, Lu, Roger Y., & Wang, Jy-An John. Grid-to-rod flow-induced impact study for PWR fuel in reactor. United States. doi:10.1016/j.pnucene.2016.06.003.
Jiang, Hao, Qu, Jun, Lu, Roger Y., and Wang, Jy-An John. 2016. "Grid-to-rod flow-induced impact study for PWR fuel in reactor". United States. doi:10.1016/j.pnucene.2016.06.003. https://www.osti.gov/servlets/purl/1319179.
@article{osti_1319179,
title = {Grid-to-rod flow-induced impact study for PWR fuel in reactor},
author = {Jiang, Hao and Qu, Jun and Lu, Roger Y. and Wang, Jy-An John},
abstractNote = {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.},
doi = {10.1016/j.pnucene.2016.06.003},
journal = {Progress in Nuclear Energy},
number = C,
volume = 91,
place = {United States},
year = {2016},
month = {6}
}