Nuclear Engineering ETDs

Publication Date

Summer 7-15-2022

Abstract

The lead-cooled fast reactor (LFR) is a fourth-generation reactor design characterized by high temperatures, neutron dosage, and highly corrosive and erosive environment due to high flow velocities. Therefore, materials testing must be performed to find structural and system components that withstand this harsh environment. These candidate alloys must have high-temperature creep strength, resistance to damage from fast-spectrum neutrons, and must grow protective oxide layers. FeCrAl alloys have been identified as possessing all these qualities, however, there are limitations due to erosion and the joining of these materials. In this work, mechanical and microstructural properties of base and conventionally joined FeCrAl-based ferritic alloys as well as additively manufactured alternatives before and after molten lead exposure at 500 C will be presented. Analysis of dissimilar joints of candidate alloys was also performed.

Keywords

FeCrAl, Molten Lead, Corrosion, Additive Manufacturing, Mechanical Testing, Tungsten Inert Gas Welding

Document Type

Thesis

Language

English

Degree Name

Nuclear Engineering

Level of Degree

Masters

Department Name

Nuclear Engineering

First Committee Member (Chair)

Dr. Osman Anderoglu

Second Committee Member

Dr. Stuart Maloy

Third Committee Member

Dr. Yu-Lin Shen

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