NSUF 16-624: Effects of carbon addition on the solute redistribution in Fe-9Cr alloys under irradiation
Fe-9Cr alloys are leading candidates for the cladding and core components in the next generation of nuclear reactors. Two of the issues that limit their lifetime at high doses are hardening at low temperatures and low doses and void swelling at high doses and intermediate temperatures. A fundamental understanding of the effects of carbon in these alloys will aid in overcoming these obstacles. Surveys of irradiation behavior of alloys by neutron and ion irradiation indicate that the nucleation and growth kinetics of radiation-induced defects are strongly influenced by the minor elemental additions. The hypothesis is that carbon-vacancy can trap small dislocation loops and prevent the migration towards sinks, and at meantime, vacancies are inclined to diffuse to voids and promote the growth of voids at intermediate temperatures. The impact of carbon addition on the accumulation of defect clusters and solute redistribution in Fe-9Cr alloys during ion irradiation is not clear. In this proposal, we will perform the post-irradiation examination for Fe-9Cr and Fe-9Cr-C alloys. The samples were irradiated at 300C to a dose of 3.2 dpa with Fe ions. We propose to use Atomic Probe Tomography (APT) in the Center for Advanced Energy Studies (CAES) at Idaho National Laboratory to study the influence of carbon on the chemical segregation in the vicinity of grain boundaries and radiation-induced dislocation loops in Fe-9Cr model alloy.
Additional Info
| Field | Value |
|---|---|
| Abstract | Fe-9Cr alloys are leading candidates for the cladding and core components in the next generation of nuclear reactors. Two of the issues that limit their lifetime at high doses are hardening at low temperatures and low doses and void swelling at high doses and intermediate temperatures. A fundamental understanding of the effects of carbon in these alloys will aid in overcoming these obstacles. Surveys of irradiation behavior of alloys by neutron and ion irradiation indicate that the nucleation and growth kinetics of radiation-induced defects are strongly influenced by the minor elemental additions. The hypothesis is that carbon-vacancy can trap small dislocation loops and prevent the migration towards sinks, and at meantime, vacancies are inclined to diffuse to voids and promote the growth of voids at intermediate temperatures. The impact of carbon addition on the accumulation of defect clusters and solute redistribution in Fe-9Cr alloys during ion irradiation is not clear. In this proposal, we will perform the post-irradiation examination for Fe-9Cr and Fe-9Cr-C alloys. The samples were irradiated at 300C to a dose of 3.2 dpa with Fe ions. We propose to use Atomic Probe Tomography (APT) in the Center for Advanced Energy Studies (CAES) at Idaho National Laboratory to study the influence of carbon on the chemical segregation in the vicinity of grain boundaries and radiation-induced dislocation loops in Fe-9Cr model alloy. |
| Award Announced Date | 2015-12-16T00:00:00 |
| Awarded Institution | Center for Advanced Energy Studies |
| Facility | Microscopy and Characterization Suite |
| Facility Tech Lead | Yaqiao Wu |
| Irradiation Facility | None |
| PI | Cheng Sun |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 624 |