Low temperature radiation-induced segregation relative to IASCC and ITER

Technical Report · Thu Sep 01 04:00:00 EDT 1994

OSTI ID:47744

Simonen, E P; Jones, R H; Charlot, L A; Bruemmer, S M ^[1]

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1. Pacific Northwest Lab., Richland, WA (United States)

Radiation induced segregation at grain boundaries in stainless steel has been evaluated as a function of temperature. Segregation caused by ion irradiation was measured and compared to temperature-dependent model predictions. The model was subsequently used to extrapolate predictions to ITER operating conditions. For ion irradiation, segregation was found to extend to temperatures below 400{degrees}C which implies that segregation is expected at temperatures less than 200{degrees}C for ITER irradiation damage rates. The model predictions were in accord with Cr depletion levels and profile widths as measured using FEG-STEM examination of ion irradiated grain boundaries. The model was further shown to be consistent with measured depletion levels at grain boundaries in 316 stainless steel irradiated in a light-water reactor at 288{degrees}C. The findings of this study suggest that chromium depletion and hence IASCC may be a concern for stainless steel structures irradiated in ITER high-temperature water environments.

• Research Organization: Oak Ridge National Lab., TN (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 47744
• Report Number(s): DOE/ER--0313/16; ON: DE95003404
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
GRAIN BOUNDARIES
ION BEAM FUSION REACTORS
IRRADIATION
PHYSICAL RADIATION EFFECTS
PROGRESS REPORT
SEGREGATION
STAINLESS STEELS
STRESS CORROSION
THERMONUCLEAR REACTOR MATERIALS