Thermal and radiation-induced segregation in model Ni-base alloys

Ab initio Based Modeling of Radiation Effects in Multi-Component Alloys: Final Scientific/Technical Report

“…As a result, the interstitial diffusion dominates RIS and leads to enrichment of Cr. This result is inconsistent with experimental results, which uniformly find Cr depletion at grain boundaries under irradiation [96].…”

University of Wisconsin Ion Beam Laboratory: A facility for irradiated materials and ion beam analysis

“…Key research includes studies on radiation damage phenomena including segregation under irradiation, radiation induced hardening in ceramics, clustering dynamics of irradiated oxide dispersion strengthened steels, nuclear fuel stability under irradiation, and surface analysis of relevant material systems [5][6][7][8][9][10][11][12][13][14][15]. Here, selected results from research conducted using the UW-IBL and CLIM are presented to demonstrate the facility's capabilities as well as selected research results.…”

Characterization techniques for assessing irradiated and ageing materials in nuclear power plant systems, structures and components (SSC)

“…It is a powerful technique to characterize grain boundary segregation (allen, Tan et al 2007, nettleship, Wild 1990 to chemically map fracture surfaces (Terachi, Fujii et al 2005) . In Fig.…”

“…During the sputtering process, not all atoms will be ionized with the same probability. 13.7 Grain boundary chromium concentration for Ni-18Cr and Ni18Cr-9Fe irradiated to 0.5 dpa from 200 to 500 °C (from Allen, Tan et al, 2007; reprinted with permission from Elsevier).…”