Microstructural examination of HT-9 irradiated in the FFTF/MOTA (Fast Flux Test Facility/Materials Open Test Assembly) to 110 dpa
- Pacific Northwest Lab., Richland, WA (USA)
- Tokai Univ., Tokyo (Japan)
The objective of this effort is to determine the applicability of martensitic stainless steels for first wall applications. HT-9 in two heat treatment conditions has been examined following irradiation at 420{degree}C to 114 dpa. The irradiations were performed in the Fast Flux Test Facility Materials Open Test Assembly (FFTF/MOTA). Void swelling is found in both conditions, with swelling values as high as 0.9% in isolated regions. Voids show a wide range of truncation, between cubic and octahedral shapes. Void swelling appears to vary as a function of preirradiation heat treatment, whereas the dislocation structure and precipitation that developed during irradiation is unaffected. Quantitative microstructural measurements are in good agreement with results on similar simple alloys. 12 refs., 4 figs., 2 tabs.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5214545
- Report Number(s):
- PNL-SA-16972; CONF-891204--12; ON: DE90004673
- Country of Publication:
- United States
- Language:
- English
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ALLOY-HT-9
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEAT TREATMENTS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MARTENSITIC STEELS
MATERIALS
MECHANICAL PROPERTIES
MICROSTRUCTURE
MOLYBDEN
MOLYBDENUM ADDITIONS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STAINLESS STEELS
STEEL-CR12MOV
STEELS
SWELLING
THERMONUCLEAR REACTOR MATERIALS
VOIDS