- Abstract:
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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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- Funding agency for:
- Project
- Type of award:
- DPhil
- Level of award:
- Doctoral
- Awarding institution:
- University of Oxford
- Copyright date:
- 2018
Thesis
Understanding the mechanisms controlling stress corrosion cracking through high-resolution characterization
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+ Engineering and Physical Sciences Research Council
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