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

Jiang, Hao; Qu, Jun; Lu, Roger Y.; Wang, Jy-An John

doi:10.1016/j.pnucene.2016.06.003

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

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Abstract

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:

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

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

Publication Date:: Fri Jun 10 00:00:00 EDT 2016

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1319179

Alternate Identifier(s):: OSTI ID: 1341209

Grant/Contract Number:: AC05-00OR22725

Resource 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

Country of Publication:: United States

Language:: English

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

Citation Formats


                    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., 2016. 
Web.  doi:10.1016/j.pnucene.2016.06.003.

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                    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.  https://doi.org/10.1016/j.pnucene.2016.06.003

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                    Jiang, Hao, Qu, Jun, Lu, Roger Y., and Wang, Jy-An John. Fri .  
"Grid-to-rod flow-induced impact study for PWR fuel in reactor".  United States.  https://doi.org/10.1016/j.pnucene.2016.06.003.  https://www.osti.gov/servlets/purl/1319179.

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@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         = {Fri Jun 10 00:00:00 EDT 2016},

  month        = {Fri Jun 10 00:00:00 EDT 2016}

}

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