Microstructural stability of a self-ion irradiated lanthana-bearing nanostructured ferritic steel

Journal Article · Wed Jul 01 00:00:00 EDT 2015 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2015.03.040· OSTI ID:1184715

Pasebani, Somayeh ^[1]; Charit, Indrajit ^[1]; Burns, Jatuporn ^[2]; Alsagabi, Sultan ^[3]; Butt, Darryl P. ^[2]; Cole, James I. ^[4]; Price, Lloyd M. ^[5]; Shao, Lin ^[5]

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1. Univ. of Idaho, Moscow, ID (United States). Dept. of Chemical and Materials Engineering; Center for Advanced Energy Studies, Idaho Falls, ID (United States)
2. Center for Advanced Energy Studies, Idaho Falls, ID (United States); Boise State Univ., ID (United States). Dept. of Materials Science and Engineering
3. Univ. of Idaho, Moscow, ID (United States). Dept. of Chemical and Materials Engineering; King Abdulaziz City for Science and Technology, Riyadh (Saudi Arabia). Atomic Energy Research Inst.
4. Center for Advanced Energy Studies, Idaho Falls, ID (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
5. Texas A & M Univ., College Station, TX (United States). Dept. of Nuclear Engineering

Thermally stable nanofeatures with high number density are expected to impart excellent high temperature strength and irradiation stability in nanostructured ferritic steels (NFSs) which have potential applications in advanced nuclear reactors. A lanthana-bearing NFS (14LMT) developed via mechanical alloying and spark plasma sintering was used in this study. The sintered samples were irradiated by Fe²⁺ ions to 10, 50 and 100 dpa at 30 °C and 500 °C. Microstructural and mechanical characteristics of the irradiated samples were studied using different microscopy techniques and nanoindentation, respectively. Overall morphology and number density of the nanofeatures remained unchanged after irradiation. Average radius of nanofeatures in the irradiated sample (100 dpa at 500 °C) was slightly reduced. A notable level of irradiation hardening and enhanced dislocation activity occurred after ion irradiation except at 30 °C and ≥50 dpa. Other microstructural features like grain boundaries and high density of dislocations also provided defect sinks to assist in defect removal.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1184715
• Report Number(s): INL/JOU-14-32947; TRN: US1500200
• Journal Information: Journal of Nuclear Materials, Vol. 462, Issue C; ISSN 0022-3115
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
77 NANOSCIENCE AND NANOTECHNOLOGY
FERRITIC STEELS
GRAIN BOUNDARIES
IRON IONS
ATOMIC DISPLACEMENTS
DISLOCATIONS
IRRADIATION
TEMPERATURE RANGE 0400-1000 K
TEMPERATURE RANGE 0273-0400 K
NANOSTRUCTURES
STABILITY
DEFECTS
SINTERING
RADIATION HARDENING
MICROSCOPY
MORPHOLOGY
REACTOR MATERIALS
LANTHANUM OXIDES
REMOVAL
SINKS
l ion irradiation
microstructural stability
nanostructured ferritc steel