Radiation Response of a 9 Cr Oxide Dispersion Strengthened Steel to Heavy Ion Irradiation
- University of Wisconsin, Madison
- Idaho National Laboratory (INL)
- ORNL
- Japan Atomic Energy Agency (JAEA)
- Pacific Northwest National Laboratory (PNNL)
Ferritic-martensitic (FM) alloys are expected to play an important role as cladding or structural components in Generation IV systems operating in the temperature range 350-700 C and to doses up to 200 dpa. Oxide dispersion strengthened (ODS) ferritic-martensitic steels have been developed to operate at higher temperatures than traditional FM steels. These steels contain nanometer-sized Y-Ti-O nanoclusters as a strengthening mechanism. Heavy ion irradiation has been used to determine the nanocluster stability over a temperature range of 500-700 C to doses of 150 dpa. At all temperatures, the average nanocluster size decreases but the nanocluster density increases. The increased density of smaller nanoclusters under radiation should lead to strengthening of the matrix. While a reduction in size under irradiation has been reported in some other studies, many report oxide stability. The data from this study are contrasted to the available literature to highlight the differences in the reported radiation response.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Shared Research Equipment Collaborative Research Center
- Sponsoring Organization:
- USDOE Office of Science (SC)
- DOE Contract Number:
- DE-AC05-00OR22725
- OSTI ID:
- 936040
- Journal Information:
- Journal of Nuclear Materials, Vol. 375, Issue 1; ISSN 0022-3115
- Country of Publication:
- United States
- Language:
- English
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