Effect of temperature on the fretting wear behavior of Cr-coated Zircaloy cladding in high-temperature pressurized water-Reference-Cited by-同舟云学术

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Effect of temperature on the fretting wear behavior of Cr-coated Zircaloy cladding in high-temperature pressurized water

Published:2023-10 Issue: Volume:584 Page:154516
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Wang Jun,Li Haojie,Li Zhengyang,Lei Yujie,Ren Quanyao,Jiao Yongjun,Cai Zhenbing

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

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

Reference61 articles.

1. A review of fretting study on nuclear power equipment;Cai;Tribol. Int.,2020

2. Irradiation-assisted stress corrosion cracking susceptibility and mechanical properties related to irradiation-induced microstructures of 304L austenitic stainless steel;Paccou;J. Nucl Mater.,2020

3. Irradiation creep and growth of zirconium alloys: a critical review;Adamson;J. Nucl Mater.,2019

4. Fretting wear comparison of cladding materials for reactor fuel cladding application;Winter;J. Nucl Mater.,2018

5. Effect of QPQ on the fretting wear behavior of TP316H steel at varying temperatures in liquid sodium;Chen;J. Nucl Mater.,2022

Cited by 10 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. High-temperature fretting wear behavior and microstructure stability of a laser-cladding Ti-Al-C-N composite coating meditated by variable cycle conditions;Tribology International;2025-01

2. Unveiling the latest progresses in chromium-coated Zircaloy cladding ATF materials: Fabrication techniques, performance metrics, and beyond;Alexandria Engineering Journal;2024-12

3. Fretting wear mechanism of nuclear fuel cladding tube under different tangential displacement;Nuclear Engineering and Design;2024-12

4. 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

5. Effect of pulse laser nitriding on the superheated steam corrosion behavior of Zr alloy;Ceramics International;2024-07

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