Radiation tolerance of alumina scale formed on FeCrAl ODS ferritic alloy-Reference-Cited by-同舟云学术

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Radiation tolerance of alumina scale formed on FeCrAl ODS ferritic alloy

Published:2021-12 Issue: Volume:29 Page:101102
ISSN:2352-1791
Container-title:Nuclear Materials and Energy
language:en
Short-container-title:Nuclear Materials and Energy

Author:

Yu Hao,Wang Haoran,Kondo Sosuke,Okuno Yasuki,Kasada Ryuta,Oono-Hori Naoko,Ukai Shigeharu

Funder

Japan Society for the Promotion of Science

Publisher

Elsevier BV

Subject

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

Reference59 articles.

1. Materials for future nuclear energy systems;Was;J. Nucl. Mater.,2019

2. Materials challenges in nuclear energy;Zinkle;Acta Mater.,2013

3. Accident tolerant fuels for LWRs: A perspective;Zinkle;J. Nucl. Mater.,2014

4. Stability domain of alumina thermally grown on Fe–Cr–Al-based model alloys and modified surface layers exposed to oxygen-containing molten Pb;Jianu;J. Nucl. Mater.,2016

5. Phase transformation of alumina coating by plasma assisted tempering of aluminized P91 steels;Jamnapara;J. Nucl. Mater.,2015

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1. Evaluation of the optimal Y content for the FeCrAl coating with excellent LBE corrosion resistance;Journal of Nuclear Materials;2024-12

2. Size dependence of micro-scale mechanical properties on heavy-ion irradiated tempered-martensitic steel evaluated through nanoindentation and micropillar compression tests;Journal of Nuclear Materials;2024-05

3. Synergistic effect of simultaneous proton irradiation and LBE corrosion on the microstructure of the FeCrAl(Y) coatings;Corrosion Science;2024-04

4. Microstructure evolution of γ-Al2O3/FeAl tritium permeation barrier coatings under 6.4 MeV Fe3+ ion irradiation;Nuclear Materials and Energy;2024-03

5. Effects of Cr and Si addition on the high-temperature oxidation resistance in high-Mn alumina-forming oxide dispersion strengthened austenitic steels;Nuclear Materials and Energy;2024-03

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