Radiation-induced grain boundary segregation in proton irradiated austenitic iron- and nickel-base alloys
- Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering
- Oak Ridge National Lab., TN (United States). Metals and Ceramics Division
Radiation-induced segregation (RIS) in austenitic iron-base and nickel-base alloys has been investigated using high energy proton irradiation. The compositions studied span the iron-rich (304 stainless steel) to nickel-rich (Inconel) regions of the Fe-Cr-Ni phase diagram. Grain boundary segregation in Fe-20Cr-24Ni, Ni-18Cr, and Ni-18Cr-9Fe irradiated between 200 C and 600 C and between 0.1 dpa and 1.0 dpa was measured and modeled using the Perks vacancy-driven continuum model describing RIS. Measurements show that segregation peaks at the highest temperature (400--500 C) in the Fe-20Cr-24Ni alloy, at an intermediate temperature (400 C) in the Ni-18Cr alloy and at the lowest temperature (300--400 C) in the Ni-18Cr-9Fe alloy. The segregation as a function of both temperature and dose is consistent with the Fe-20Cr24Ni alloy having the slowest Cr-vacancy migration rate. The Perks model is shown to accurately predict segregation trends only if alloy specific diffusion parameters are used. This requirement for alloy-specific diffusion parameters limits the ability of the Perks model to predict segregation in new alloy systems.
- DOE Contract Number:
- AC05-84OR21400; AC05-76OR00033
- OSTI ID:
- 203769
- Report Number(s):
- CONF-950816--; ISBN 1-877914-95-9
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
AUSTENITIC STEELS
CHROMIUM
ELECTRON MICROSCOPY
EXPERIMENTAL DATA
INCONEL ALLOYS
MATHEMATICAL MODELS
NICKEL-CHROMIUM STEELS
PHYSICAL RADIATION EFFECTS
RADIATION DOSES
REACTOR MATERIALS
TEMPERATURE DEPENDENCE
TEMPERATURE RANGE 0400-1000 K
VACANCIES
WATER COOLED REACTORS