Nuclear Engineering ETDs

Publication Date

Fall 12-13-2025

Abstract

Alloy 709, a 20Cr25Ni alloy, is an advanced austenitic steel designed for next generation sodium fast reactors. Preliminary studies have shown the potential of Alloy 709 in sodium fast reactors. In this study, Precipitate Treated Alloy 709 specimens are irradiated with 2 MeV H+ at 500 °C from 0.0057 dpa to 1.7 dpa. Electron microscopy characterization techniques are used to understand the effects of radiation on mechanical properties as well as microstructure of Alloy 709. The microstructure did not show formation of voids, amorphization of precipitates, or increase in grain size up to 1.7 dpa. Correspondingly nano-indentation and micro-pillar compression do not show any discernable change due to irradiation. Surface Cr segregation is observed following high temperature irradiation exposure. This work offers insights into the understanding of Alloy 709 property degradation under high temperature irradiation environments to determine its effectiveness for use in a sodium fast reactor.

Keywords

Alloy 709, radiation damage, nano mechanical testing, proton irradiation, nuclear material

Document Type

Thesis

Language

English

Degree Name

Nuclear Engineering

Level of Degree

Masters

Department Name

Nuclear Engineering

First Committee Member (Chair)

Eric Lang

Second Committee Member

Mohamed El-genk

Third Committee Member

Madura Pathirage

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