Microstructural aspect of irradiation assisted stress corrosion cracking of LWR in-core structural materials
Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review
Author(s)
Detail(s)
Original language | English |
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Pages (from-to) | 171-188 |
Journal / Publication | Radiation Effects and Defects in Solids |
Volume | 144 |
Issue number | 1-4 |
Publication status | Published - 1998 |
Externally published | Yes |
Link(s)
Abstract
Microstructural evolution of proton-irradiated austenitic stainless steels and Inconel 600 alloy were studied in the temperature range interesting to light water reactor (LWR) core conditions. Radiation-induced solute segregation was observed in all irradiation temperatures at dose of 0.1 dpa and above. Constant extension rate test (CERT) was performed to study the irradiation-assisted stress corrosion cracking (IASCC) behavior of these alloys. Void swelling, dislocation and loop structures, and phase transformation were studied to understand the relationship of microstructural evolution to the IASCC phenomenon. It is found that in low carbon austenitic stainless steels, the γ → α phase transformation could play an important role in stress corrosion cracking mechanism. Twining dislocations were observed in 304L specimens irradiated at 230°C to 1 dpa.
Research Area(s)
- Austenitic stainless steel, CERT, IASCC, Irradiation, Microstructure, RIS
Citation Format(s)
Microstructural aspect of irradiation assisted stress corrosion cracking of LWR in-core structural materials. / Kai, J.I.-Jung; Tsai, Chuen-Horng; Liu, Wen-Jen.
In: Radiation Effects and Defects in Solids, Vol. 144, No. 1-4, 1998, p. 171-188.
In: Radiation Effects and Defects in Solids, Vol. 144, No. 1-4, 1998, p. 171-188.
Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review