Irradiation hardening of FeCrAl ODS alloys with Zr/Hf addition after high-energy self-ions irradiation

Irradiation hardening of FeCrAl ODS alloys with Zr/Hf addition after high-energy self-ions irradiation

FeCrAl ODS steel is the promising candidate cladding material for the accident tolerant fuel (ATF) of the light water reactors (LWR), due to the formation of Al2O3 in alloys which could suppress the oxidation reaction with hot steam. In the present work, change in microstructures and the correspondi...

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Bibliographic Details
Main Authors: Xuxiao Han, Chonghong Zhang, Mengke Niu, Tieshan Wang, Akihiko Kimura
Format: Article
Language:English
Published: Elsevier 2023-12-01
Series:Nuclear Materials and Energy
Subjects:
FeCrAl ODS alloys
Zr/Hf addition
Irradiation hardening
Sink strength
Dislocation loops
DBH model
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179123001953

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http://www.sciencedirect.com/science/article/pii/S2352179123001953

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