Corrosion behavior of ferritic FeCrAl alloys in simulated BWR normal water chemistry-Reference-Cited by-同舟云学术

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Corrosion behavior of ferritic FeCrAl alloys in simulated BWR normal water chemistry

Published:2021-03 Issue: Volume:545 Page:152744
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Wang Peng^ORCID,Grdanovska Slavica,Bartels David M.,Was Gary S.

Funder

U.S. Department of Energy

Publisher

Elsevier BV

Subject

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

Reference44 articles.

1. Overview of the U.S. DOE accident tolerant fuel development program;Carmack;LWR Fuel Perform. Meet. Top Fuel,2013

2. Effect of radiation damage and water radiolysis on corrosion of FeCrAl alloys in hydrogenated water;Wang;J. Nucl. Mater.,2020

3. Hydrogen permeation in FeCrAl alloys for LWR cladding application;Hu;J. Nucl. Mater.,2015

4. In-situ irradiation accelerated oxidation of Zircaloy-4 under proton or electron irradiation in PWR primary water;Wang,2015

5. Oxidation of Zircaloy-4 during in situ proton irradiation and corrosion in PWR primary water;Wang;J. Mater. Res.,2015

Cited by 18 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. Effect of irradiation on the corrosion of 304 stainless steel in pressurized water reactor (PWR) simulated water chemistry;Corrosion Science;2024-09

2. A facility for studying corrosion via in-situ Raman spectroscopy;Journal of Nuclear Materials;2024-07

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

4. Comparing the oxidation of FeCrAl alloys in isothermal and cyclic high-temperature steam environments;Journal of Nuclear Materials;2024-02

5. Insights into oxidation and nitridation of alumina-forming FeCrAl alloy after supercritical water exposure: Effect of pre-corrosion on high-temperature damage behavior;The Journal of Supercritical Fluids;2023-10

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