Development of a Predictive Wear Model for Grid-to-Rod Fretting in Light Water Nuclear Reactors-Reference-Cited by-同舟云学术

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Development of a Predictive Wear Model for Grid-to-Rod Fretting in Light Water Nuclear Reactors

Published:2013-03-08 Issue: Volume: Page:139-158
ISSN:
Container-title:Tribo-Corrosion: Research, Testing, and Applications
language:
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Author:

Blau Peter J.¹,Hayrapetian Areg V.²,Demkowicz Michael J.³

Affiliation:

1. Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831-6063, US.

2. Dept. of Mechanical Engineering, Massachusetts Institute of Technology, Cambridge, MA 02139, US.

3. Dept. of Materials Science and Engineering, Massachusetts Institute of Technology, Cambridge, MA 02139, US.

Publisher

ASTM International

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Tribocorrosion in Pressurized High-Temperature Water: A Mass Flow Model Based on the Third-Body Approach;Tribology Letters;2016-03-04

2. A multi-stage wear model for grid-to-rod fretting of nuclear fuel rods;Wear;2014-05

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