Microstructure and Mechanical Properties of Ferritic/Martensitic Steel EP-823 after Neutron Irradiation to High Doses in BOR-60
Short-term mechanical properties and microstructure of ferritic/martensitic steel EP-823 were investigated following irradiation as fuel pin cladding in BOR-60 to 63 dpa at 365-680?. Ring specimens cut from the cladding were used for ring-pull tests and electron microscopy. Up to {approx}460? irradiated EP-823 was found to fracture in a brittle mode at low strength levels. With increasing temperature the total elongation increased to 27.5 %. The irradiated strength in the temperature range 460-670? was found to be close to its unirradiated value. Void formation in EP-823 was suppressed with isolated voids observed only at 375? to 50.5 dpa. After irradiation at 375 and 500? finely dispersed ?6? precipitates formed. At 500 and 630? equiaxed -phase formed in ferritic grains and plate-like ?2? precipitates, which were present in the starting microstructure, dissolved completely.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-76RL01830
- OSTI ID:
- 860068
- Report Number(s):
- PNNL-SA-40770; AT6020100; TRN: US200523%%196
- Resource Relation:
- Conference: 11th International Conference on Fusion Reactor Materials in JOURNAL OF NUCLEAR MATERIALS , 329-33 PT. A AND B(314-318; Elsevier Science ,Amsterdam,Netherlands.
- Country of Publication:
- United States
- Language:
- English
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