Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors-Reference-Cited by-同舟云学术

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Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors

Published:2021-10 Issue: Volume:554 Page:153090
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Yin Liang,Jurewicz T.B.,Larsen M.,Drobnjak M.^ORCID,Graff C.C.,Lutz D.R.,Rebak R.B.^ORCID

Funder

US Department of Energy

Publisher

Elsevier BV

Subject

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

Reference16 articles.

1. [2006], “Corrosion or Zirconium Alloy Components in Light Water Reactors,”;Lemaignan,2006

2. Uniform corrosion behavior of FeCrAl alloys in borated lithiated high temperature water;Ning;J. Mater. Sci. Technol.,2021

3. Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding;Raiman;J. Nucl. Mater.,2020

4. Alloy Selection for Accident Tolerant Fuel Cladding in Commercial Light Water Reactors;Rebak;Metall. Mater. Trans. E,2015

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

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

2. Post irradiation examinations of Fecral cladding in PWR conditions;Journal of Nuclear Materials;2024-09

3. Corrosion behavior of additively manufactured FeCrAl in out-of-pile light water reactor environments;npj Materials Degradation;2024-08-28

4. Source term analysis of FeCrAl accident tolerant fuel using MELCOR;Annals of Nuclear Energy;2024-07

5. Corrosion of FeCrAl-1 Nb alloy in deaerated water at 290 ℃ and 7 MPa: The oxidation behavior of grain boundary;Corrosion Science;2024-07

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