Effect of Al concentration on Fe-17Cr alloy during steam oxidation at 400 °C-Reference-Cited by-同舟云学术

Effect of Al concentration on Fe-17Cr alloy during steam oxidation at 400 °C

Published:2023-06 Issue: Volume:217 Page:111135
ISSN:0010-938X
Container-title:Corrosion Science
language:en
Short-container-title:Corrosion Science

Author:

Roy Indranil^ORCID,Abouelella Hamdy^ORCID,Rajendran Rupesh^ORCID,Chikhalikar Atharva S.,Larsen Michael,Umretiya Rajnikant^ORCID,Hoffman Andrew,Rebak Raul^ORCID

Funder

US Department of Energy

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference22 articles.

1. Accident tolerant fuels for LWRs: a perspective;Zinkle;J. Nucl. Mater.,2014

2. Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants;Rebak;EPJ Nucl. Sci. Technol.,2017

3. Accident tolerant fuel cladding development: Promise, status, and challenges;Terrani;J. Nucl. Mater.,2018

4. Selection of fuel cladding material for nuclear fission reactors;de;Eng. Fail. Anal.,2011

5. Corrosion issues in nuclear industry today;Cattant;Mater. Today,2008

Cited by 9 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. Additive manufacturing of FeCrAl alloys for nuclear applications - A focused review;Nuclear Materials and Energy;2024-09

2. Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys;Journal of Nuclear Materials;2024-09

3. Oxide Layers in Ni-doped FeCrAl Alloy in 320°C Radioactive Hydrogenated Water;Journal of Nuclear Materials;2024-05

4. Hydrogen embrittlement of FeCrAl alloys: The significant role of Laves phase and AlN particles;Materials Science and Engineering: A;2024-04

5. Distinctive Oxide Films Develop on the Surface of FeCrAl as the Environment Changes for Nuclear Fuel Cladding;Corrosion and Materials Degradation;2024-03-18