Experimental research progress of grid to rod fretting in pressurized water reactors
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference140 articles.
1. Review of Fuel Failures in Water Cooled Reactors (2006–2015);Agency,2019
2. Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding;Alat;J. Nucl. Mater.,2016
3. The effect of Zircaloy-4 substrate surface condition on the adhesion strength and corrosion of SiC coatings;Al-Olayyan;J. Nucl. Mater.,2005
4. Effect of zinc injection on the electrochemical behavior and crack growth rate of a 316 L stainless steel in simulated primary coolant of pressurized water reactors;Arjmand;Mater. Charact.,2021
5. Fretting wear of Zr-alloy pressure tubes under the combined effects of in-plane and out-of-plane flow-induced vibrations;Attia;Wear,2005
Cited by 3 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. Autoclave grid-to-rod fretting corrosion behaviors of the Zr alloy fuel cladding with and without Cr coating through advanced characterization;Corrosion Science;2024-10
2. Fretting wear behaviors of Cr-coated Zr–1Nb alloy cladding tube mated with Zr-4 alloy dimple under different tangential displacements;Wear;2024-06
3. Experimental and numerical research on flow-induced vibration characteristics of Hydraulic Suspended Passive Shutdown Subassembly in SFR;Progress in Nuclear Energy;2024-05
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