Effect of dispersion particles and precipitates on the corrosion properties of ODS-Cu, Cu-Cr-Zr and Cu-Cr alloys in Na2SO4 solutions-Reference-Cited by-同舟云学术

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Effect of dispersion particles and precipitates on the corrosion properties of ODS-Cu, Cu-Cr-Zr and Cu-Cr alloys in Na2SO4 solutions

Published:2022-06 Issue: Volume:31 Page:101159
ISSN:2352-1791
Container-title:Nuclear Materials and Energy
language:en
Short-container-title:Nuclear Materials and Energy

Author:

Hatakeyama Masahiko,Okada Kai,Sunada Satoshi,Sato Koichi

Funder

Japan Society for the Promotion of Science

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics

Reference31 articles.

1. Specification of properties and design allowables for copper alloys used in HHF components of ITER;Kalinin;J. Nucl. Mater.,2002

2. Specification of CuCrZr alloy properties after various thermo-mechanical treatments and design allowables including neutron irradiation effects;Barabash;J. Nucl. Mater.,2011

3. Low void swelling in dispersion strengthened copper alloys under single-ion irradiation;Hatakeyama;J. Nucl. Mater.,2002

4. 200 MeV proton irradiation of the oxide-dispersion-strengthened copper alloy (GlidCop-Al15);Simos;J. Nucl. Mater.,2019

5. Evaluation of irradiation hardening in ODS-Cu and non ODS-Cu by nanoindentation hardness test and micro-pillar compression test after self-ion irradiation;Liu;Nucl. Mater. Energy,2021

Cited by 6 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. Consequence of coherent Cu₅Zr precipitates and Cu₂O passive layer formation on the corrosive behaviour of additively processed Cu-Cr-Zr alloy in simulated seawater;Physica Scripta;2024-09-02

2. Comparative studies of different solutes effects on microstructure and comprehensive performance of coherent precipitation-strengthened Cu–Ni–Al alloys;Journal of Materials Research and Technology;2024-05

3. Effect of process control agent on the synthesis of Cu-Y2O3 by mechanical alloying;Nuclear Materials and Energy;2024-03

4. Evaluation of hydrogen embrittlement in ODS-Cu, Cu–Cr–Zr, and Cu–Cr alloys using slow strain rate technique test;Nuclear Materials and Energy;2024-03

5. Microstructure and properties of Cu-Cr-Zr alloy by doping Sc;Materials Letters;2023-04

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