Investigating grid-to-rod fretting wear of nuclear fuel claddings using a unique autoclave fretting rig-Reference-Cited by-同舟云学术

Investigating grid-to-rod fretting wear of nuclear fuel claddings using a unique autoclave fretting rig

Published:2018-10 Issue: Volume:412-413 Page:30-37
ISSN:0043-1648
Container-title:Wear
language:en
Short-container-title:Wear

Author:

Lazarevic Sladjan,Lu Roger Y.,Favede Cyrille,Plint George,Blau Peter J.,Qu Jun

Funder

U.S. Department of Energy

Publisher

Elsevier BV

Subject

Materials Chemistry,Surfaces, Coatings and Films,Surfaces and Interfaces,Mechanics of Materials,Condensed Matter Physics

Reference23 articles.

1. A fretting damage analysis of railway axle;Zhang;Adv. Mater. Res.,2013

2. M. Kennard, D. Sunderland, J.A. Harbottle, Study of Grid-to-Rod Fretting Wear in PWR Fuel Assembly, Stoller Report, April, 1995.

3. R.Y. Lu, M.E. Conner, M.L. Boone, C.L. Wilbur, R. Marshall, Nuclear fuel assembly flow-induced vibration and endurance testing, in: Proceedings of the Symposium on Flow-Induced Vibration – 2001 ASME Pressure Vessels and Piping Conference, July 22–26, Atlanta, Georgia, 2001.

4. Fretting-wear of zirconium alloys;Fisher;Nucl. Eng. Des.,2002

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