Thesis
Mechanical behaviour of irradiated tungsten for fusion power
- Abstract:
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Tungsten will be a key material for the plasma-facing components in future fusion devices. Its mechanical performance under neutron irradiation will strongly influence the lifetime of these devices. Pure tungsten has been subjected to a variety of irradiating species - tungsten ions, helium ions and fission neutrons - between 500°C and 900°C and the change in mechanical properties measured by micro-mechanical testing methods.
Pure tungsten has been ion-irradiated using self-ions and...
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- Files:
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(bin, 13.6MB, Terms of use)
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Authors
Contributors
+ Roberts, S
- Division:
- MPLS
- Department:
- Materials
- Role:
- Supervisor
+ Armstrong, D
- Division:
- MPLS
- Department:
- Materials
- Role:
- Supervisor
- Publication date:
- 2015
- DOI:
- Type of award:
- DPhil
- Level of award:
- Doctoral
- Awarding institution:
- Oxford University, UK
- Language:
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English
- Keywords:
- Subjects:
- UUID:
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uuid:400a6537-2fc2-4298-821d-b73a84f1f52b
- Local pid:
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ora:12227
- Deposit date:
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2015-09-08
- ARK identifier:
Terms of use
- Copyright holder:
- Gibson, J
- Copyright date:
- 2015
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