Published September 1992 | Version v1
Journal article

Radiation-induced segregation in FFTF-irradiated austentic stainless steels

  • 1. Metals and Ceramics Div., Oak Ridge National Lab., TN (United States)
  • 2. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

Description

Analytical electron microscopy has been applied to radiation-induced segregation (RIS) to defect sinks in two austenitic stainless steels irradiated in the Fast Flux Test Facility to ≅ 15 dpa at 520deg C. RIS to faulted dislocation loops has been shown to be strongly dependent on loop size. Several mechanisms for this effect are discussed, including increased vacancy-driven RIS for large dislocation loop sizes. The spatial distribution of solutes near large dislocation loops is consistent with dominance of the inverse Kirkendall effect and not with an interstitial mechanism of RIS. In a nickel-stabilized austenite (USPCA), RIS to grain boundaries results in nickel enrichment and chromium depletion. In a manganese-stabilized austenite (EP838), manganese is the species strongly depleted at boundaries, resulting in little chromium depletion relative to that in USPCA. Therefore, EP838 should exhibit greater resistance to radiation-induced sensitization. Manganese depletion at grain boundaries in the EP838 may induce a loss of austenite stability, but that effect will be offset in part by an enrichment of nickel. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
191-194
Journal Issue
pt.B
Journal Page Range
p. 1331-1335.
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
5. international conference on fusion reactor materials (ICFRM-5).
Dates
17-22 Nov 1991.
Place
Clearwater, FL (United States).