\"Nuclear reactor materials are subjected to a harsh environment including high temperatures and radiation fluences. In order to extend the lifetime of current light water reactors (LWRs) and realize the development of advanced Gen IV nuclear reactors new materials must be developed which can withstand such an environment. This thesis involves two approaches to solving this materials problem: advanced manufacturing of current commercial alloys using severe plastic deformation (SPD) and the development of new advanced high entropy alloys (HEAs).
Because SPD is effective at achieving grain refinement, this technique was used to obtain material having a high volume fraction of grain boundaries which act as effective radiation induced defect sinks. This work aims to study the pre-irradiation microstructure and irradiation tolerance of nanostructured 304 produced using SPD.
HEAs have been theorized to have retarded diffusion which prevents large voids and dislocation loops from forming in addition to their good phase stability. Most HEA compositions, however, contain Co which activates under irradiation and can cause concerns over waste management. This work studies two compositions of Co-free HEAs and evaluates their performance under ion irradiation\"--Abstract, page iv.
","abstract_html":"<p>"Nuclear reactor materials are subjected to a harsh environment including high temperatures and radiation fluences. In order to extend the lifetime of current light water reactors (LWRs) and realize the development of advanced Gen IV nuclear reactors new materials must be developed which can withstand such an environment. This thesis involves two approaches to solving this materials problem: advanced manufacturing of current commercial alloys using severe plastic deformation (SPD) and the development of new advanced high entropy alloys (HEAs).</p> <p>Because SPD is effective at achieving grain refinement, this technique was used to obtain material having a high volume fraction of grain boundaries which act as effective radiation induced defect sinks. This work aims to study the pre-irradiation microstructure and irradiation tolerance of nanostructured 304 produced using SPD.</p> <p>HEAs have been theorized to have retarded diffusion which prevents large voids and dislocation loops from forming in addition to their good phase stability. Most HEA compositions, however, contain Co which activates under irradiation and can cause concerns over waste management. This work studies two compositions of Co-free HEAs and evaluates their performance under ion irradiation"--Abstract, page iv.</p>","abstract_has_math":false,"creators":["Hoffman, Andrew Kalevi"],"institution":"Missouri University of Science and Technology","degree_name":"Ph. D. in Nuclear Engineering","degree_level":null,"degree_discipline":null,"degree_department":null,"school":null,"contributors":[],"advisors":[],"committee_chairs":[],"committee_members":[],"year":null,"date_issued":"","date_published":null,"updated_at":"2026-07-24T03:18:34Z","subjects":["Nanocrystalline Materials","Segregation","Atom Probe Tomography","Severe Plastic Deformation","Diffusion","High Pressure Torsion","Radiation Induced Segregation","Materials Science and Engineering","Nuclear Engineering"],"languages":[],"rights":[],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://scholarsmine.mst.edu/doctoral_dissertations/2833","outbound_label":"Repository record","outbound_source":"dc:identifier"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:creator","label":"Author","values":["Hoffman, Andrew Kalevi"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:type","label":"Dc Type","values":["Dissertation - Open Access"]},{"key":"thesis:degree_name","label":"Degree Name","values":["Ph. D. in Nuclear Engineering"]},{"key":"thesis:institution_name","label":"Thesis Institution Name","values":["Missouri University of Science and Technology"]}]},{"id":"subjects_keywords","label":"Subjects and Keywords","entries":[{"key":"dc:subject","label":"Dc Subject","values":["Nanocrystalline Materials","Segregation","Atom Probe Tomography","Severe Plastic Deformation","Diffusion","High Pressure Torsion","Radiation Induced Segregation","Materials Science and Engineering","Nuclear Engineering"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier","label":"Identifier","values":["https://scholarsmine.mst.edu/doctoral_dissertations/2833"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description.abstract","label":"Abstract","values":["\"Nuclear reactor materials are subjected to a harsh environment including high temperatures and radiation fluences. In order to extend the lifetime of current light water reactors (LWRs) and realize the development of advanced Gen IV nuclear reactors new materials must be developed which can withstand such an environment. This thesis involves two approaches to solving this materials problem: advanced manufacturing of current commercial alloys using severe plastic deformation (SPD) and the development of new advanced high entropy alloys (HEAs).
Because SPD is effective at achieving grain refinement, this technique was used to obtain material having a high volume fraction of grain boundaries which act as effective radiation induced defect sinks. This work aims to study the pre-irradiation microstructure and irradiation tolerance of nanostructured 304 produced using SPD.
HEAs have been theorized to have retarded diffusion which prevents large voids and dislocation loops from forming in addition to their good phase stability. Most HEA compositions, however, contain Co which activates under irradiation and can cause concerns over waste management. This work studies two compositions of Co-free HEAs and evaluates their performance under ion irradiation\"--Abstract, page iv.
"]},{"key":"dc:title","label":"Title","values":["Development and characterization of nanostructured steels and high entropy alloys for nuclear applications"]}]}],"canonical_facts":{"dc:creator":["Hoffman, Andrew Kalevi"],"dc:description.abstract":["\"Nuclear reactor materials are subjected to a harsh environment including high temperatures and radiation fluences. In order to extend the lifetime of current light water reactors (LWRs) and realize the development of advanced Gen IV nuclear reactors new materials must be developed which can withstand such an environment. This thesis involves two approaches to solving this materials problem: advanced manufacturing of current commercial alloys using severe plastic deformation (SPD) and the development of new advanced high entropy alloys (HEAs).
Because SPD is effective at achieving grain refinement, this technique was used to obtain material having a high volume fraction of grain boundaries which act as effective radiation induced defect sinks. This work aims to study the pre-irradiation microstructure and irradiation tolerance of nanostructured 304 produced using SPD.
HEAs have been theorized to have retarded diffusion which prevents large voids and dislocation loops from forming in addition to their good phase stability. Most HEA compositions, however, contain Co which activates under irradiation and can cause concerns over waste management. This work studies two compositions of Co-free HEAs and evaluates their performance under ion irradiation\"--Abstract, page iv.
"],"dc:identifier":["https://scholarsmine.mst.edu/doctoral_dissertations/2833"],"dc:subject":["Nanocrystalline Materials","Segregation","Atom Probe Tomography","Severe Plastic Deformation","Diffusion","High Pressure Torsion","Radiation Induced Segregation","Materials Science and Engineering","Nuclear Engineering"],"dc:title":["Development and characterization of nanostructured steels and high entropy alloys for nuclear applications"],"dc:type":["Dissertation - Open Access"],"thesis:degree_name":["Ph. D. in Nuclear Engineering"],"thesis:institution_name":["Missouri University of Science and Technology"]},"updated_at":"2026-07-24T03:18:34Z"}