Proton irradiation induced grain boundary segregation in austenitic stainless steels
- Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering
- Pacific Northwest Lab., Richland, WA (United States)
Radiation induced segregation (RIS) has been implicated as a mechanism for irradiation-assisted stress corrosion cracking (IASCC) in reactor core components. Proton irradiation has been shown to be useful in creating grain boundary chemistries similar to those found in neutron and charged particle irradiated materials from accelerated testing of IASCC susceptibility. This work quantifies grain boundary RIS as a function of proton irradiation dose (0.1-3.0 dpa), temperature (200--600 C), and alloy composition (20Cr-9Ni, 24Cr-19Ni, and xCr-24Ni, x = 16, 20, 24). Auger electron spectroscopy revealed Cr depletion and Ni enrichment under all irradiation conditions. As a function of dose, the degree of segregation increased rapidly to near saturation prior to 1 dpa, with a boundary composition of 12.1 at.% Cr and 36.0 at.% Ni at 1 dpa. Segregation peaked at approximately 500 C with 13.0 at.%Cr and 38.6 at.% Ni at the grain boundary at 0.5 dpa; very little segregation was observed at or below 300 C or at 600 C. The trends in segregation as a function of dose agreed well with the Perks` model predictions with the exception of measurement at 600 C, which showed the sharp decrease in segregation predicted for a higher temperature (700 C--800 C). For alloys containing constant bulk Cr but varying Ni, the Perks` model agreed well with the observed segregation trend; however, for alloys containing constant bulk Ni and varying cr, agreement was achieved only through the use of composition dependent diffusion parameters.
- DOE Contract Number:
- FG02-93ER12130; AC06-76RL01830; FG06-89ER75522
- OSTI ID:
- 99433
- Report Number(s):
- CONF-941144-; ISBN 1-55899-275-8; TRN: 95:019091
- Resource Relation:
- Conference: Fall meeting of the Materials Research Society (MRS), Boston, MA (United States), 28 Nov - 9 Dec 1994; Other Information: PBD: 1995; Related Information: Is Part Of Microstructure of irradiated materials; Robertson, I.M. [ed.] [Univ. of Illinois, Urbana, IL (United States). Dept. of Materials Science and Engineering]; Rehn, L.E. [ed.] [Argonne National Lab., IL (United States). Materials Science Div.]; Zinkle, S.J. [ed.] [Oak Ridge National Lab., TN (United States). Metals and Ceramics Div.]; Phythian, W.J. [ed.] [AEA Technology-Harwell, Oxon (United Kingdom)]; PB: 588 p.; Materials Research Society symposium proceedings, Volume 373
- Country of Publication:
- United States
- Language:
- English
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