{"id":{"repo_id":"uiuc","oai_identifier":"oai:www.ideals.illinois.edu:2142/121294"},"canonical_url":"https://search.dev.ndltd.org/etd/uiuc/oai:www.ideals.illinois.edu:2142/121294","repository":{"repo_id":"uiuc","name":"University of Illinois - Urbana-Champaign","base_url":"https://www.ideals.illinois.edu/oai-pmh"},"display":{"title":"The efficacy of a porous w/liquid Li hybrid system as a self-healing, adaptive plasma-material interface in future plasma-burning nuclear fusion reactors","abstract":"Submission published under a 24 month embargo labeled 'U of I Access', the embargo will last until 2025-08-01","abstract_html":"Submission published under a 24 month embargo labeled 'U of I Access', the embargo will last until 2025-08-01","abstract_has_math":false,"creators":["Kapat, Aveek S"],"institution":"University of Illinois at Urbana-Champaign","degree_name":"Ph.D.","degree_level":"Dissertation","degree_discipline":"Nuclear, Plasma, Radiolgc Engr","degree_department":null,"school":null,"contributors":["Allain, Jean Paul","Curreli, Davide","Ruzic, David","Miljkovic, Nenad"],"advisors":[],"committee_chairs":[],"committee_members":[],"year":2023,"date_issued":"2023-08","date_published":"2023-08","updated_at":"2026-07-22T22:24:57Z","subjects":["Porous Tungsten","Liquid Lithium","Plasma-facing Components","D Retention","Interfacial Phenomena","Vapor Shielding"],"languages":["en","eng"],"rights":["© 2023 Aveek S. Kapat"],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://hdl.handle.net/2142/121294","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","Ruzic, David","Miljkovic, Nenad"]},{"key":"dc:creator","label":"Author","values":["Kapat, Aveek S"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date","label":"Dc Date","values":["2023-08","2023-05-16"]},{"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":["Dissertation"]},{"key":"thesis:degree_name","label":"Degree Name","values":["Ph.D."]},{"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":["Porous Tungsten","Liquid Lithium","Plasma-facing Components","D Retention","Interfacial Phenomena","Vapor Shielding"]}]},{"id":"language_rights","label":"Language and Rights","entries":[{"key":"dc:language","label":"Dc Language","values":["en","eng"]},{"key":"dc:rights","label":"Dc Rights","values":["© 2023 Aveek S. Kapat"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier","label":"Identifier","values":["https://hdl.handle.net/2142/121294"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description","label":"Description","values":["Submission published under a 24 month embargo labeled 'U of I Access', the embargo will last until 2025-08-01","The student, Aveek Kapat, accepted the attached license on 2023-05-05 at 12:36.","The student, Aveek Kapat, submitted this Dissertation for approval on 2023-05-05 at 13:03.","This Dissertation was approved for publication on 2023-05-16 at 09:11.","DSpace SAF Submission Ingestion Package generated from Vireo submission #19356 on 2023-12-04 at 17:17:43","The tungsten surface in a fusion reactor is subject to the steady-state heat flux 10−15MW , and a particle flux of 1E24 ions/m^2s . These high heat and particle fluxes can result in recrystallization, surface morphology, and W erosion, which must stay below 20ppm to prevent radiative cooling of the core. The focus of this work is to develop a material system that has the favorable bulk properties of W while reducing the impact of Plasma- Material Interactions (PMI) on tungsten by introducing an interface material that is compatible with both the impinging plasma as well as the structural W below the interface. One such system is a porous tungsten-liquid metal hybrid system, having the bulk, thermomechanical properties of a high defect sink tungsten foam, that have demonstrated such in inertial fusion while being a scaffold for a liquid metal (Li in the case of this study) with favorable PMI properties. The purpose of this study is to determine the efficacy of this hybrid material system as a plasma interface,by examining the feasibility of porous tungsten, made via a spark plasma sintering process, as a stable structure for incorporation of a liquid metal as well as a passive flow media for liquid lithium. Additionally, determination of PMI effects on this system, and a quantitative study of liquid/vapor Li interface are also examined. Liquid Li compatibility is tested two different ways: surface wetting/imbibition will be determined by static wetting angle measurements at surface temperature range from 200°C to 400°C within a vacuum environment of the Materials Characterization Test Stand (MCATS) at the University of Illinois. D inventory and depth profile in porous W substrates with 1μm Li deposited and melted is quantified with in-operando NRA during 60eV D+ plasma exposure to a fluence 2E24 ions/m^2 with the retention behaviour relative to lithium percolation quantified with in-operando He Elastic Recoil Detection. Finally, a 1-D drift diffusion model to study and quantify the extent of surface protection due to heat flux dissipation via a radiative vapor shield is under development using applications belonging to the Multiphysics Object- Oriented Simulation Environment (MOOSE) will be discussed."]},{"key":"dc:format","label":"Dc Format","values":["application/pdf"]},{"key":"dc:title","label":"Title","values":["The efficacy of a porous w/liquid Li hybrid system as a self-healing, adaptive plasma-material interface in future plasma-burning nuclear fusion reactors"]}]}],"canonical_facts":{"dc:contributor":["Allain, Jean Paul","Curreli, Davide","Ruzic, David","Miljkovic, Nenad"],"dc:creator":["Kapat, Aveek S"],"dc:date":["2023-08","2023-05-16"],"dc:description":["Submission published under a 24 month embargo labeled 'U of I Access', the embargo will last until 2025-08-01","The student, Aveek Kapat, accepted the attached license on 2023-05-05 at 12:36.","The student, Aveek Kapat, submitted this Dissertation for approval on 2023-05-05 at 13:03.","This Dissertation was approved for publication on 2023-05-16 at 09:11.","DSpace SAF Submission Ingestion Package generated from Vireo submission #19356 on 2023-12-04 at 17:17:43","The tungsten surface in a fusion reactor is subject to the steady-state heat flux 10−15MW , and a particle flux of 1E24 ions/m^2s . These high heat and particle fluxes can result in recrystallization, surface morphology, and W erosion, which must stay below 20ppm to prevent radiative cooling of the core. The focus of this work is to develop a material system that has the favorable bulk properties of W while reducing the impact of Plasma- Material Interactions (PMI) on tungsten by introducing an interface material that is compatible with both the impinging plasma as well as the structural W below the interface. One such system is a porous tungsten-liquid metal hybrid system, having the bulk, thermomechanical properties of a high defect sink tungsten foam, that have demonstrated such in inertial fusion while being a scaffold for a liquid metal (Li in the case of this study) with favorable PMI properties. The purpose of this study is to determine the efficacy of this hybrid material system as a plasma interface,by examining the feasibility of porous tungsten, made via a spark plasma sintering process, as a stable structure for incorporation of a liquid metal as well as a passive flow media for liquid lithium. Additionally, determination of PMI effects on this system, and a quantitative study of liquid/vapor Li interface are also examined. Liquid Li compatibility is tested two different ways: surface wetting/imbibition will be determined by static wetting angle measurements at surface temperature range from 200°C to 400°C within a vacuum environment of the Materials Characterization Test Stand (MCATS) at the University of Illinois. D inventory and depth profile in porous W substrates with 1μm Li deposited and melted is quantified with in-operando NRA during 60eV D+ plasma exposure to a fluence 2E24 ions/m^2 with the retention behaviour relative to lithium percolation quantified with in-operando He Elastic Recoil Detection. Finally, a 1-D drift diffusion model to study and quantify the extent of surface protection due to heat flux dissipation via a radiative vapor shield is under development using applications belonging to the Multiphysics Object- Oriented Simulation Environment (MOOSE) will be discussed."],"dc:format":["application/pdf"],"dc:identifier":["https://hdl.handle.net/2142/121294"],"dc:language":["en","eng"],"dc:rights":["© 2023 Aveek S. Kapat"],"dc:subject":["Porous Tungsten","Liquid Lithium","Plasma-facing Components","D Retention","Interfacial Phenomena","Vapor Shielding"],"dc:title":["The efficacy of a porous w/liquid Li hybrid system as a self-healing, adaptive plasma-material interface in future plasma-burning nuclear fusion reactors"],"dc:type":["text"],"thesis:degree_discipline":["Nuclear, Plasma, Radiolgc Engr"],"thesis:degree_level":["Dissertation"],"thesis:degree_name":["Ph.D."],"thesis:institution_name":["University of Illinois at Urbana-Champaign"]},"updated_at":"2026-07-22T22:24:57Z"}