Modeling of complex wear behavior associated with grid-to-rod fretting in light water nuclear reactors

Blau, P. J.; Qu, J.; Lu, R.

doi:10.1007/s11837-016-2113-9

Title: Modeling of complex wear behavior associated with grid-to-rod fretting in light water nuclear reactors

Abstract

One significant concern in the operation of light water nuclear reactors is the fretting wear damage to fuel cladding from flow-induced vibrations. For years, research on the grid-to-rod fretting (GTRF) phenomena has been underway in countries where nuclear power production is a significant industry. Under the auspices of the U.S. Department of Energy Consortium for Advanced Simulation of Light Water Reactors, an effort has been underway to develop and test an engineering wear model for zirconium alloy fuel rod cladding against a supporting grid. Furthermore, the multi-stage model accounts for oxide layers and wear rate transitions. Our paper describes the basis for a GTRF engineering wear model, the physical significance of the wear factor it contains, and recent progress toward model validation based on a fretting wear testing apparatus that accounts for coolant temperature, pressure, and the presence of periodic impacts (gaps) in grid/rod contact.

Authors:

Blau, P. J. ^[1]; Qu, J. ^[2]; Lu, R. ^[3]

Bluau Tribology Consulting, Enka, NC (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Westinghouse Electric Company, LLC, Columbia, SC (United States)

Publication Date:: Wed Sep 21 00:00:00 EDT 2016

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

Sponsoring Org.:: USDOE

OSTI Identifier:: 1327602

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: JOM. Journal of the Minerals, Metals & Materials Society

Additional Journal Information:: Journal Volume: 68; Journal Issue: 11; Journal ID: ISSN 1047-4838

Publisher:: Springer

Country of Publication:: United States

Language:: English

Subject:: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

Citation Formats


                    Blau, P. J., Qu, J., and Lu, R. Modeling of complex wear behavior associated with grid-to-rod fretting in light water nuclear reactors.  United States: N. p., 2016. 
Web.  doi:10.1007/s11837-016-2113-9.

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                    Blau, P. J., Qu, J., & Lu, R. Modeling of complex wear behavior associated with grid-to-rod fretting in light water nuclear reactors.  United States.  https://doi.org/10.1007/s11837-016-2113-9

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                    Blau, P. J., Qu, J., and Lu, R. Wed .  
"Modeling of complex wear behavior associated with grid-to-rod fretting in light water nuclear reactors".  United States.  https://doi.org/10.1007/s11837-016-2113-9.  https://www.osti.gov/servlets/purl/1327602.

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@article{osti_1327602,

  title        = {Modeling of complex wear behavior associated with grid-to-rod fretting in light water nuclear reactors},

  author       = {Blau, P. J. and Qu, J. and Lu, R.},

  abstractNote = {One significant concern in the operation of light water nuclear reactors is the fretting wear damage to fuel cladding from flow-induced vibrations. For years, research on the grid-to-rod fretting (GTRF) phenomena has been underway in countries where nuclear power production is a significant industry. Under the auspices of the U.S. Department of Energy Consortium for Advanced Simulation of Light Water Reactors, an effort has been underway to develop and test an engineering wear model for zirconium alloy fuel rod cladding against a supporting grid. Furthermore, the multi-stage model accounts for oxide layers and wear rate transitions. Our paper describes the basis for a GTRF engineering wear model, the physical significance of the wear factor it contains, and recent progress toward model validation based on a fretting wear testing apparatus that accounts for coolant temperature, pressure, and the presence of periodic impacts (gaps) in grid/rod contact.},

  doi          = {10.1007/s11837-016-2113-9},

  journal      = {JOM. Journal of the Minerals, Metals & Materials Society},

  number       = 11,

  volume       = 68,

  place        = {United States},

  year         = {Wed Sep 21 00:00:00 EDT 2016},

  month        = {Wed Sep 21 00:00:00 EDT 2016}

}

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Cited by: 11 works

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Works referenced in this record:

Contact and Rubbing of Flat Surfaces
journal, August 1953

Archard, J. F.
Journal of Applied Physics, Vol. 24, Issue 8
DOI: 10.1063/1.1721448

Fretting-wear of zirconium alloys
journal, April 2002

Fisher, Nigel J.; Weckwerth, Murray K.; Grandison, Dwight A. E.
Nuclear Engineering and Design, Vol. 213, Issue 1
DOI: 10.1016/S0029-5493(02)00035-3

Fretting wear behavior of a nuclear fuel rod under a simulated primary coolant condition
journal, April 2013

Lee, Young-Ho; Kim, Hyung-Kyu
Wear, Vol. 301, Issue 1-2
DOI: 10.1016/j.wear.2013.01.067

The study on grid-to-rod fretting wear models for PWR fuel
journal, December 2009

Kim, Kyu-Tae
Nuclear Engineering and Design, Vol. 239, Issue 12
DOI: 10.1016/j.nucengdes.2009.08.018

On fretting maps
journal, September 1988

Vingsbo, Olof; Söderberg, Staffan
Wear, Vol. 126, Issue 2
DOI: 10.1016/0043-1648(88)90134-2

A multi-stage wear model for grid-to-rod fretting of nuclear fuel rods
journal, May 2014

Blau, Peter J.
Wear, Vol. 313, Issue 1-2
DOI: 10.1016/j.wear.2014.02.016

Comparative study on rod fretting behavior of different spacer spring geometries
journal, January 2009

Kovács, Szilárd; Stabel, Jürgen; Ren, Mingmin
Wear, Vol. 266, Issue 1-2
DOI: 10.1016/j.wear.2008.06.010

Overview no. 55 Wear-Mechanism maps
journal, January 1987

Lim, S. C.; Ashby, M. F.
Acta Metallurgica, Vol. 35, Issue 1
DOI: 10.1016/0001-6160(87)90209-4

Mixed fretting regime
journal, March 1995

Zhou, Z. R.; Vincent, L.
Wear, Vol. 181-183
DOI: 10.1016/0043-1648(95)90168-X

Fretting wear of laterally supported tube
journal, October 2001

Kim, Hyung-Kyu; Kim, Seon-Jae; Yoon, Kyung-Ho
Wear, Vol. 250, Issue 1-12
DOI: 10.1016/S0043-1648(01)00634-2

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Similar Records

Title: Modeling of complex wear behavior associated with grid-to-rod fretting in light water nuclear reactors

Abstract

Citation Formats

Contact and Rubbing of Flat Surfaces journal, August 1953

Fretting-wear of zirconium alloys journal, April 2002

Fretting wear behavior of a nuclear fuel rod under a simulated primary coolant condition journal, April 2013

The study on grid-to-rod fretting wear models for PWR fuel journal, December 2009

On fretting maps journal, September 1988

A multi-stage wear model for grid-to-rod fretting of nuclear fuel rods journal, May 2014

Comparative study on rod fretting behavior of different spacer spring geometries journal, January 2009

Overview no. 55 Wear-Mechanism maps journal, January 1987

Mixed fretting regime journal, March 1995

Fretting wear of laterally supported tube journal, October 2001

Contact and Rubbing of Flat Surfaces
journal, August 1953

Fretting-wear of zirconium alloys
journal, April 2002

Fretting wear behavior of a nuclear fuel rod under a simulated primary coolant condition
journal, April 2013

The study on grid-to-rod fretting wear models for PWR fuel
journal, December 2009

On fretting maps
journal, September 1988

A multi-stage wear model for grid-to-rod fretting of nuclear fuel rods
journal, May 2014

Comparative study on rod fretting behavior of different spacer spring geometries
journal, January 2009

Overview no. 55 Wear-Mechanism maps
journal, January 1987

Mixed fretting regime
journal, March 1995

Fretting wear of laterally supported tube
journal, October 2001