Effects of oversized solutes on radiation-induced segregation in austenitic stainless steels
作者： M.J. Hackett , J.T. Busby , M.K. Miller , G.S. Was
DOI: 10.1016/J.JNUCMAT.2009.02.010
关键词:
摘要: Zirconium or hafnium additions to austenitic stainless steels caused a reduction in grain boundary Cr depletion after proton irradiations for up 3 dpa at 400 °C and 1 500 °C. The predictions of radiation-induced segregation (RIS) model were also consistent with experiments showing greater effectiveness Zr relative Hf due larger binding energy. However, the showed that solute disappeared above loss increasing dose is attributed amount oversized from matrix growth carbide precipitates. Atom probe tomography measurements indicated solution as function irradiation dose. observations supported by diffusion analysis suggesting significant vacancy flux precipitate surfaces occurs on time scales irradiations. With decrease available solution, improved agreement between RIS solute-vacancy trapping process, mechanism enhanced recombination suppression RIS.
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