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Journal ArticleDOI

A review of fretting study on nuclear power equipment

TLDR
In this article, the research status of fretting damage in key equipment and structures of nuclear power plant is reviewed, and the authors have solved many problems, accumulated a lot of experience, and put forward many criteria.
About
This article is published in Tribology International.The article was published on 2020-04-01. It has received 78 citations till now. The article focuses on the topics: Fretting & Nuclear power plant.

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Surface integrity in metal machining - Part II: Functional performance

TL;DR: In this paper, the interplay between the metallurgical and micro-mechanical condition induced by material removal processes and their in-service response is thoroughly explored, by a critical analysis of the state-of-the-art in the field.
Journal ArticleDOI

Progress in studying the fretting wear/corrosion of nuclear steam generator tubes

TL;DR: In this paper, the authors reviewed the current understanding of the response of nuclear steam generator tube materials (Alloy 600, Alloy 690 and Alloy 800) to fretting wear, focusing on the effects of environment factors (temperature, pH and oxygen content), mechanical parameters (sliding amplitude, normal force and frequency) and materials state (grain size, carbide volume fraction, size and distribution, and surface treatment).
Journal ArticleDOI

Study on the fretting maps of Zircaloy-4 alloy against Inconel 718 alloy

TL;DR: Fretting wear tests of Zircaloy-4 alloy against Inconel 718 alloy were conducted on a fretting wear rig as discussed by the authors, where the contact state and fretting running characteristics were investigated.
Journal ArticleDOI

Effect of the frequency on fretting corrosion behavior between Alloy 690TT tube and 405 stainless steel plate in high temperature pressurized water

TL;DR: In this article, the effect of fretting frequency on fretting corrosion behavior between Alloy 690TT heat-exchanger tube and 405 stainless steel plate in simulated secondary water of nuclear power plants was investigated.
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Carbon-based electrocatalysts for CO2 electroreduction produced via MOF, biomass, and other precursors carbonization: A review

TL;DR: In this article, the authors highlight the advances in CO2RR electrocatalysis using nanocarbons derived from MOFs, biomass, polymers, and other precursors, assessing the aspects to improve.
References
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Journal ArticleDOI

Materials Challenges in Nuclear Energy

TL;DR: In this article, the three major materials challenges for the current and next generation of water-cooled fission reactors are centered on two structural materials aging degradation issues (corrosion and stress corrosion cracking of structural materials and neutron-induced embrittlement of reactor pressure vessels), along with improved fuel system reliability and accident tolerance issues.
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Ferritic/martensitic steels for next-generation reactors

TL;DR: In this article, the authors investigated the use of elevated-temperature ferritic/martensitic steels for in-core and out-of-core applications for the next generation of nuclear power reactors.
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Accident tolerant fuels for LWRs: A perspective

TL;DR: In this article, three general strategies for accident tolerant fuels are explored: modification of current state-of-the-art zirconium alloy cladding to further improve oxidation resistance (including use of coatings), replacement of Zr Alloy cladding with an alternative oxidation resistant high-performance cladding, and replacement of the monolithic ceramic oxide fuel with alternative fuel forms.
Journal ArticleDOI

Accident tolerant fuel cladding development: Promise, status, and challenges

TL;DR: A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding and silicon carbide fiber-reinforced SCCM composite, is offered in this paper.
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