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Understanding the mechanisms controlling stress corrosion cracking through high-resolution characterization

Abstract:

Austenitic alloys have been extensively used in the nuclear industry as structural components due to their combination of excellent mechanical properties and high corrosion resistance. Although these alloys have a good service record, many can become susceptible to stress corrosion cracking (SCC) under pressurized water reactor (PWR) primary water conditions. After several decades of study, a considerable number of factors have been revealed that affect SCC susceptibility, such as material...

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Division:
MPLS
Department:
Materials
Role:
Author

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Supervisor
China Scholarship Council More from this funder
Engineering and Physical Sciences Research Council More from this funder
Type of award:
DPhil
Level of award:
Doctoral
Awarding institution:
University of Oxford
UUID:
uuid:d7e96930-9eaf-4994-b182-675a58ed556a
Deposit date:
2019-04-24

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