A multi-stage wear model for grid-to-rod fretting of nuclear fuel rods-Reference-Cited by-同舟云学术

A multi-stage wear model for grid-to-rod fretting of nuclear fuel rods

Published:2014-05 Issue:1-2 Volume:313 Page:89-96
ISSN:0043-1648
Container-title:Wear
language:en
Short-container-title:Wear

Author:

Blau Peter J.

Publisher

Elsevier BV

Subject

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

Reference31 articles.

1. CASL virtual reactor predictive simulation: grid-to-rod fretting wear;Lu;J. Metals,2011

2. A study on grid-to-rod fretting wear models for PWR fuel;Kim;Nucl. Eng. Design,2009

3. Development of a Predictive Wear Model for Grid-to-Rod Fretting in Light Water Nuclear Reactors, in Tribo-Corrosion: Research, Testing and Applications, ASTM STP 1563;Blau,2013

4. Consortium for Advanced Simulation of Light Water Reactors (CASL), U.S. Department of Energy, website: 〈http://www.casl.gov〉.

5. CASL-Supported Research in Progress;Heyrapetian,2012

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