Nuclear Engineering ETDs

Publication Date

Spring 5-16-2026

Abstract

Lead–lithium eutectic (LLE) is a leading candidate coolant and tritium breeder for fusion reactor blankets due to its favorable heat transfer properties and high tritium breeding ratio. However, LLE is highly corrosive and, in the strong magnetic fields present in fusion reactors, experiences magnetohydrodynamic (MHD) effects that can produce significant pressure drops and flow instabilities. Understanding corrosion behavior in these extreme environments is essential for assessing the viability of LLE blanket systems. This work presents the design and construction of a forced-convection LLE corrosion loop to study corrosion behavior at temperatures up to 425 °C and flow velocities up to 1 m/s in the presence of an external magnetic field (~1.5 T). The loop incorporates instrumentation including a differential pressure transducer to enable measurements of MHD pressure drop and flow-accelerated corrosion. This experimental platform will support future studies of material degradation in high-temperature LLE systems relevant to blanket environments.

Keywords

Lead-Lithium Eutectic, Magnetohydrodynamics, Experimental Design, Fusion Blankets, Corrosion

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. Minghui Chen

Third Committee Member

Dr. Fernando Garzon

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