Effect of Irradiation on Strengthening of a Model Fe-9Cr Oxide Dispersion Strengthened Alloy
- 1. Boise State University, 1910 University Dr., Boise, ID 83725 (United States)
Description
The growing energy demand will increasingly call upon advanced nuclear reactors to supply safe and reliable energy worldwide. However, structural and cladding materials in these reactors will be subject to extreme conditions of up to a few hundred displacements per atom (dpa) at temperatures as high as 600 deg. C. Oxide dispersion strengthened (ODS) alloys are leading candidates for these components because their dispersion of Y-Ti-O nanoclusters provides high strength at elevated temperatures and dimensional stability under irradiation. But recent work has suggested that the oxides are unstable under irradiation, which has serious implications on mechanical performance. Thus, the objective of this work is to understand the change in strengthening mechanisms of an Fe-9Cr ODS alloy under irradiation. We use two approaches to assess strengthening of a proton-irradiated and neutron-irradiated Fe-9Cr ODS. First, nanoindentation directly measures changes in yield strength. Second, microstructure measurements are passed through models of two strengthening mechanisms. Results of these two approaches are compared to infer the strengthening mechanisms in the irradiated ODS alloy. A model Fe-9Cr ODS steel was irradiated to 3 dpa at 500 deg. C using either 2.0 MeV protons or a fast neutron spectrum. Both irradiation types induced the formation of dislocation loops and voids. Both proton and neutron irradiation resulted in dissolution of oxide nanoclusters, though neutron irradiation led to much more extensive oxide nano-cluster dissolution. The irradiated microstructure was used to predict irradiation hardening by considering both the precipitation strengthening and solid solution strengthening mechanisms. Due to more extensive oxide nano-cluster dissolution under neutron irradiation, the solid solution strengthening mechanism must be considered in order for the predicted change in yield strength to be comparable to that measured by nanoindentation. (authors)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 114
- Journal Issue
- 1
- Journal Page Range
- p. 1255-1257
- ISSN
- 0003-018X
Conference
- Title
- Annual Meeting of the American Nuclear Society. Embedded topical meeting 'Nuclear fuels and structural material for the next generation nuclear reactors'
- Dates
- 12-16 Jun 2016
- Place
- New Orleans, LA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52032401
- Subject category
- S36: MATERIALS SCIENCE; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATOMIC DISPLACEMENTS; FAST NEUTRONS; IRRADIATION; MICROSTRUCTURE; NANOSTRUCTURES; NEUTRON SPECTRA; PRECIPITATION; REACTORS; SOLID SOLUTIONS; STABILITY; STEELS; YIELD STRENGTH
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; DISPERSIONS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; HOMOGENEOUS MIXTURES; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; MIXTURES; NEUTRONS; NUCLEONS; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; SEPARATION PROCESSES; SOLUTIONS; SPECTRA; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 3 refs.; Available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 United States