{"id":{"repo_id":"uiuc","oai_identifier":"oai:www.ideals.illinois.edu:2142/120179"},"canonical_url":"https://search.dev.ndltd.org/etd/uiuc/oai:www.ideals.illinois.edu:2142/120179","repository":{"repo_id":"uiuc","name":"University of Illinois - Urbana-Champaign","base_url":"https://www.ideals.illinois.edu/oai-pmh"},"display":{"title":"Advanced thermo-mechanical and plasma-material interaction characterization and testing methodologies of tungsten-based materials for neutron-relevant environments","abstract":"Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2023-09-01 without embargo terms","abstract_html":"Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2023-09-01 without embargo terms","abstract_has_math":false,"creators":["Reid, Nate Clark"],"institution":"University of Illinois at Urbana-Champaign","degree_name":"M.S.","degree_level":"Thesis","degree_discipline":"Nuclear, Plasma, Radiolgc Engr","degree_department":null,"school":null,"contributors":["Allain, Jean Paul","Curreli, Davide"],"advisors":[],"committee_chairs":[],"committee_members":[],"year":2023,"date_issued":"2023-05","date_published":"2023-05","updated_at":"2026-07-22T22:24:56Z","subjects":["Tungsten","Neutron","Mechanical","Plasma","Brittle"],"languages":["en","eng"],"rights":["Copyright 2023 Nathan Clark Reid"],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://hdl.handle.net/2142/120179","outbound_label":"Handle","outbound_source":"dc:identifier"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor","label":"Contributor","values":["Allain, Jean Paul","Curreli, Davide"]},{"key":"dc:creator","label":"Author","values":["Reid, Nate Clark"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date","label":"Dc Date","values":["2023-05","2023-05-05"]},{"key":"dc:type","label":"Dc Type","values":["text"]},{"key":"thesis:degree_discipline","label":"Discipline","values":["Nuclear, Plasma, Radiolgc Engr"]},{"key":"thesis:degree_level","label":"Degree Level","values":["Thesis"]},{"key":"thesis:degree_name","label":"Degree Name","values":["M.S."]},{"key":"thesis:institution_name","label":"Thesis Institution Name","values":["University of Illinois at Urbana-Champaign"]}]},{"id":"subjects_keywords","label":"Subjects and Keywords","entries":[{"key":"dc:subject","label":"Dc Subject","values":["Tungsten","Neutron","Mechanical","Plasma","Brittle"]}]},{"id":"language_rights","label":"Language and Rights","entries":[{"key":"dc:language","label":"Dc Language","values":["en","eng"]},{"key":"dc:rights","label":"Dc Rights","values":["Copyright 2023 Nathan Clark Reid"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier","label":"Identifier","values":["https://hdl.handle.net/2142/120179"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description","label":"Description","values":["Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2023-09-01 without embargo terms","The student, Nate Reid, accepted the attached license on 2023-05-04 at 17:46.","The student, Nate Reid, submitted this Thesis for approval on 2023-05-05 at 09:42.","This Thesis was approved for publication on 2023-05-05 at 11:28.","DSpace SAF Submission Ingestion Package generated from Vireo submission #19343 on 2023-09-01 at 16:56:20","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)."]},{"key":"dc:format","label":"Dc Format","values":["application/pdf"]},{"key":"dc:title","label":"Title","values":["Advanced thermo-mechanical and plasma-material interaction characterization and testing methodologies of tungsten-based materials for neutron-relevant environments"]}]}],"canonical_facts":{"dc:contributor":["Allain, Jean Paul","Curreli, Davide"],"dc:creator":["Reid, Nate Clark"],"dc:date":["2023-05","2023-05-05"],"dc:description":["Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2023-09-01 without embargo terms","The student, Nate Reid, accepted the attached license on 2023-05-04 at 17:46.","The student, Nate Reid, submitted this Thesis for approval on 2023-05-05 at 09:42.","This Thesis was approved for publication on 2023-05-05 at 11:28.","DSpace SAF Submission Ingestion Package generated from Vireo submission #19343 on 2023-09-01 at 16:56:20","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)."],"dc:format":["application/pdf"],"dc:identifier":["https://hdl.handle.net/2142/120179"],"dc:language":["en","eng"],"dc:rights":["Copyright 2023 Nathan Clark Reid"],"dc:subject":["Tungsten","Neutron","Mechanical","Plasma","Brittle"],"dc:title":["Advanced thermo-mechanical and plasma-material interaction characterization and testing methodologies of tungsten-based materials for neutron-relevant environments"],"dc:type":["text"],"thesis:degree_discipline":["Nuclear, Plasma, Radiolgc Engr"],"thesis:degree_level":["Thesis"],"thesis:degree_name":["M.S."],"thesis:institution_name":["University of Illinois at Urbana-Champaign"]},"updated_at":"2026-07-22T22:24:56Z"}