Applicability of out-of-pile fretting wear tests to in-reactor fretting wear-induced failure time prediction-Reference-Cited by-同舟云学术

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Applicability of out-of-pile fretting wear tests to in-reactor fretting wear-induced failure time prediction

Published:2013-02 Issue:1-3 Volume:433 Page:364-371
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kim Kyu-Tae

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference22 articles.

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

2. K. Kim, Fuel Failure Analysis of Kori-2 Cycle 8, KAERI/TR-339/93, 1993.

3. K. Donovan, Fuel integrity initiative overview, in: ANS LWR Fuel Performance Conference, San Francisco, USA, 2007.

4. A study on the grid-to-rod fretting wear-induced fuel failure observed in the 16×16KOFA fuel

5. Nuclear Fuel Performance Simulation and UQ;Montgomery,2011

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1. A validated numerical methodology for flow-induced vibration of a semi-spherical end cantilever rod in axial flow;Physics of Fluids;2024-07-01

2. Review of spacer grid to rod fretting in pressurized water reactor;Nuclear Engineering and Design;2024-03

3. Grid-to-rod fretting in nuclear power reactors: Driving mechanisms, research methodologies and mitigation measures;Journal of Nuclear Materials;2023-12

4. Experimental research progress of grid to rod fretting in pressurized water reactors;Annals of Nuclear Energy;2023-10

5. Effects of Normal Load, Thickness of Oxide Layer and Number of Cycles on Fretting Wear of PWR Fuel ROD Cladding;Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 2;2023

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