Advanced thermo-mechanical and plasma-material interaction characterization and testing methodologies of tungsten-based materials for neutron-relevant environments

Before a first-of-a-kind fusion power plant can be built to deliver high yield, carbon-free energy to the electrical grid, fusion science will need to address the challenges involved with materials that can handle the extreme conditions of fusion nuclear reactions. Tungsten (W)-based materials are strong candidates to be able to handle the particle and heat loads from the fusion plasma that are sent to the region where tungsten armors, known as the divertor. These W-based materials should be qualified through plasma-material interaction (PMI) studies and thermo-mechanical testing. In this work, surface characterization techniques for plasma-facing components (PFCs) and a design for a surface science analysis chamber are proposed for a prototype Material Plasma Exposure eXperiment (MPEX) facility designed for the purpose of in-situ PMI studies on a linear plasma device. Studies addressing the mechanical testing of tungsten performed with regards to neutron pre- and post-irradiation examinations are discussed and performed. The issue of neutron interactions, such as transmutation, and how to measure impurity concentrations at the surface-level and in bulk W with respect to material depth is explored. Tying the lessons learned from these experiments, an interesting materials challenge is presented which W heated in the presence of graphite will cause embrittlement in thin W materials such as foils and fibers for W engineered composites, and the carbon degradation is characterized. These studies will lay the foundation for further investigations into W-based material property investigations into PMI and thermo-mechanical properties with experiments using state of the art neutron irradiation facilities such as MPEX, High Flux Isotope Reactor (HFIR), and the Low-Activation Materials Development and Analysis (LAMDA) Laboratory at Oak Ridge National Laboratory (ORNL).

Name thesis:degree_name

M.S.

Level thesis:degree_level

Thesis

Discipline thesis:degree_discipline

Nuclear, Plasma, Radiolgc Engr

Grantor

University of Illinois at Urbana-Champaign

Year dc:date

2023

Author dc:creator

• Reid, Nate Clark

Contributors dc:contributor

• Allain, Jean Paul
• Curreli, Davide

• Tungsten
• Neutron
• Mechanical
• Plasma
• Brittle

Statement dc:rights

• Copyright 2023 Nathan Clark Reid

Language dc:language

en, eng

Handle dc:identifier

https://hdl.handle.net/2142/120179

OAI record oai:identifier

https://www.ideals.illinois.edu/oai-pmh?verb=GetRecord&metadataPrefix=etdms&identifier=oai%3Awww.ideals.illinois.edu%3A2142%2F120179