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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 PengORCID,Grdanovska Slavica,Bartels David M.,Was Gary S.

Funder

U.S. Department of Energy

Publisher

Elsevier BV

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
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