Microstructural evolution of heavy-ion irradiated HT-9 ferritic steel
- National Tsing-Hua Univ. (Taiwan)
Ferritic and martensitic steel HT-9 is considered to be the leading candidate for the cladding and structural materials of fast breeder reactors (FBRs) and the first walls and blankets in conceptual fusion reactor designs for its superior resistance to void swelling and adequate mechanical properties at elevated temperatures. This study was designed to investigate the microstructural stability, including precipitation response, void swelling, and dislocation evolution, of HT-9 following heavy-ion irradiation at elevated temperatures. The most significant result obtained in this study is that without helium implantation, there is virtually no void swelling in all specimens following heavy ion irradiation to a peak damage level of 200 dpa in the temperature range between 300 and 600{degree}C. Even with 100 appm helium preimplantation, the void swelling rate in HT-9 specimens is <0.01% per dpa, which is much better swelling resistance than 1% per dpa, which is much better swelling resistance than 1% per dpa for austenitic stainless steels (e.g., Type 316 or 304 stainless steel). This superior void swelling resistance suggested that the void swelling may not be the critical problem for using the HT-9 alloy in FBRs or fusion reactors.
- OSTI ID:
- 6502773
- Report Number(s):
- CONF-891103--
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 60; ISSN TANSA; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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ALLOY-HT-9
ALLOYS
BREEDER REACTORS
BREEDING BLANKETS
CHARGED PARTICLES
CHROMIUM ALLOYS
CHROMIUM STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL DEFECTS
CRYSTAL STRUCTURE
DISLOCATIONS
ELECTRON MICROSCOPY
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FIRST WALL
FLUIDS
FUEL CANS
GASES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HELIUM
HIGH ALLOY STEELS
ION IMPLANTATION
IONS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
LINE DEFECTS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MARTENSITIC STEELS
MATERIALS
MECHANICAL PROPERTIES
METALLOGRAPHY
MICROSCOPY
MICROSTRUCTURE
MOLYBDEN
MOLYBDENUM ADDITIONS
NICKEL IONS
NONMETALS
PHYSICAL RADIATION EFFECTS
PRECIPITATION
RADIATION EFFECTS
RARE GASES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
SEPARATION PROCESSES
STABILITY
STAINLESS STEELS
STEEL-CR12MOV
STEELS
SWELLING
TEMPERATURE DEPENDENCE
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TRANSMISSION ELECTRON MICROSCOPY