{"id":{"repo_id":"uiuc","oai_identifier":"oai:www.ideals.illinois.edu:2142/90650"},"canonical_url":"https://search.dev.ndltd.org/etd/uiuc/oai:www.ideals.illinois.edu:2142/90650","repository":{"repo_id":"uiuc","name":"University of Illinois - Urbana-Champaign","base_url":"https://www.ideals.illinois.edu/oai-pmh"},"display":{"title":"Steam oxidation of FeCrAl coated Zircaloy-2","abstract":"A NEITZCH Jupiter 441 simultaneous thermal analysis with a water vapor furnace was installed and calibrated for temperature and di fferential scanning calorimetry (DSC). Bare and FeCrAl coated Zircaloy-2 nuclear fuel cladding and FeCrAl coated single crystal Yttria stabilized Zirconia (YSZ) samples were oxidized in an argon/steam environment at 700 C and 1100 C. FeCrAl coated Zircaloy-2 was also heated to 1200 C in an inert environment. Real-time thermo gravimetric analysis (TGA) and DSC data was taken during the steam oxidation. Glancing angle and 2 theta-omega X-ray di raction (XRD) scans were taken of the samples pre- and post- exposure. Scanning electron microscopy, energy-dispersive X-ray spectroscopy, and Auger electron spectroscopy (AES) depth profiling was performed. The TGA showed that the coated Zircaloy-2 samples experienced significantly less weight gain as compared to the bare Zircaloy-2 samples, indicating a slower rate of oxidation. AES and XRD showed that at 700 C this decrease was due to the formation of a protective alpha -alumina layer. Chromium segregated below the alumina layer to form a secondary layer. Finally it was observed that iron di fused into the base Zircaloy-2. At 1100 C a eutectic interaction between the zirconium and iron on the Zr exists and is postulated to have caused the evaporation of the coating and loss of protection. The FeCrAl on YSZ samples did not exhibit this phenomenon, however a spinel oxide was formed at 1100 C as opposed to alpha-alumina.","abstract_html":"A NEITZCH Jupiter 441 simultaneous thermal analysis with a water vapor furnace was installed and calibrated for temperature and di fferential scanning calorimetry (DSC). Bare and FeCrAl coated Zircaloy-2 nuclear fuel cladding and FeCrAl coated single crystal Yttria stabilized Zirconia (YSZ) samples were oxidized in an argon/steam environment at 700 C and 1100 C. FeCrAl coated Zircaloy-2 was also heated to 1200 C in an inert environment. Real-time thermo gravimetric analysis (TGA) and DSC data was taken during the steam oxidation. Glancing angle and 2 theta-omega X-ray di raction (XRD) scans were taken of the samples pre- and post- exposure. Scanning electron microscopy, energy-dispersive X-ray spectroscopy, and Auger electron spectroscopy (AES) depth profiling was performed. The TGA showed that the coated Zircaloy-2 samples experienced significantly less weight gain as compared to the bare Zircaloy-2 samples, indicating a slower rate of oxidation. AES and XRD showed that at 700 C this decrease was due to the formation of a protective alpha -alumina layer. Chromium segregated below the alumina layer to form a secondary layer. Finally it was observed that iron di fused into the base Zircaloy-2. At 1100 C a eutectic interaction between the zirconium and iron on the Zr exists and is postulated to have caused the evaporation of the coating and loss of protection. The FeCrAl on YSZ samples did not exhibit this phenomenon, however a spinel oxide was formed at 1100 C as opposed to alpha-alumina.","abstract_has_math":false,"creators":["Mouche, Peter A."],"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":["Heuser, Brent J."],"advisors":[],"committee_chairs":[],"committee_members":[],"year":2016,"date_issued":"2016-07-07T19:58:01Z","date_published":"2016-07-07T19:58:01Z","updated_at":"2026-07-22T22:26:34Z","subjects":["Oxidation","Cladding","Nuclear","Accident","Coating","FeCrAl","Steam"],"languages":["en"],"rights":["Copyright 2016 Peter Mouche"],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"http://hdl.handle.net/2142/90650","outbound_label":"Handle","outbound_source":"dc:identifier"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor","label":"Contributor","values":["Heuser, Brent J."]},{"key":"dc:creator","label":"Author","values":["Mouche, Peter A."]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date","label":"Dc Date","values":["2016-07-07T19:58:01Z","2016-04-29","2016-05"]},{"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":["Oxidation","Cladding","Nuclear","Accident","Coating","FeCrAl","Steam"]}]},{"id":"language_rights","label":"Language and Rights","entries":[{"key":"dc:language","label":"Dc Language","values":["en"]},{"key":"dc:rights","label":"Dc Rights","values":["Copyright 2016 Peter Mouche"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier","label":"Identifier","values":["http://hdl.handle.net/2142/90650"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description","label":"Description","values":["A NEITZCH Jupiter 441 simultaneous thermal analysis with a water vapor furnace was installed and calibrated for temperature and di fferential scanning calorimetry (DSC). Bare and FeCrAl coated Zircaloy-2 nuclear fuel cladding and FeCrAl coated single crystal Yttria stabilized Zirconia (YSZ) samples were oxidized in an argon/steam environment at 700 C and 1100 C. FeCrAl coated Zircaloy-2 was also heated to 1200 C in an inert environment. Real-time thermo gravimetric analysis (TGA) and DSC data was taken during the steam oxidation. Glancing angle and 2 theta-omega X-ray di raction (XRD) scans were taken of the samples pre- and post- exposure. Scanning electron microscopy, energy-dispersive X-ray spectroscopy, and Auger electron spectroscopy (AES) depth profiling was performed. The TGA showed that the coated Zircaloy-2 samples experienced significantly less weight gain as compared to the bare Zircaloy-2 samples, indicating a slower rate of oxidation. AES and XRD showed that at 700 C this decrease was due to the formation of a protective alpha -alumina layer. Chromium segregated below the alumina layer to form a secondary layer. Finally it was observed that iron di fused into the base Zircaloy-2. At 1100 C a eutectic interaction between the zirconium and iron on the Zr exists and is postulated to have caused the evaporation of the coating and loss of protection. The FeCrAl on YSZ samples did not exhibit this phenomenon, however a spinel oxide was formed at 1100 C as opposed to alpha-alumina.","Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2016-07-07 without embargo terms","The student, Peter Mouche, accepted the attached license on 2016-04-25 at 16:50.","The student, Peter Mouche, submitted this Thesis for approval on 2016-04-25 at 17:04.","This Thesis was approved for publication on 2016-04-29 at 08:50.","DSpace SAF Submission Ingestion Package generated from Vireo submission #9488 on 2016-07-07 at 13:33:04","Made available in DSpace on 2016-07-07T19:58:01Z (GMT). No. of bitstreams: 2 MOUCHE-THESIS-2016.pdf: 9232383 bytes, checksum: 7a24ea6f443cc1f40d8e83d580172108 (MD5) LICENSE.txt: 4209 bytes, checksum: c03e1855a770fab318387b5de5a7180c (MD5) Previous issue date: 2016-04-29"]},{"key":"dc:format","label":"Dc Format","values":["application/pdf"]},{"key":"dc:title","label":"Title","values":["Steam oxidation of FeCrAl coated Zircaloy-2"]}]}],"canonical_facts":{"dc:contributor":["Heuser, Brent J."],"dc:creator":["Mouche, Peter A."],"dc:date":["2016-07-07T19:58:01Z","2016-04-29","2016-05"],"dc:description":["A NEITZCH Jupiter 441 simultaneous thermal analysis with a water vapor furnace was installed and calibrated for temperature and di fferential scanning calorimetry (DSC). Bare and FeCrAl coated Zircaloy-2 nuclear fuel cladding and FeCrAl coated single crystal Yttria stabilized Zirconia (YSZ) samples were oxidized in an argon/steam environment at 700 C and 1100 C. FeCrAl coated Zircaloy-2 was also heated to 1200 C in an inert environment. Real-time thermo gravimetric analysis (TGA) and DSC data was taken during the steam oxidation. Glancing angle and 2 theta-omega X-ray di raction (XRD) scans were taken of the samples pre- and post- exposure. Scanning electron microscopy, energy-dispersive X-ray spectroscopy, and Auger electron spectroscopy (AES) depth profiling was performed. The TGA showed that the coated Zircaloy-2 samples experienced significantly less weight gain as compared to the bare Zircaloy-2 samples, indicating a slower rate of oxidation. AES and XRD showed that at 700 C this decrease was due to the formation of a protective alpha -alumina layer. Chromium segregated below the alumina layer to form a secondary layer. Finally it was observed that iron di fused into the base Zircaloy-2. At 1100 C a eutectic interaction between the zirconium and iron on the Zr exists and is postulated to have caused the evaporation of the coating and loss of protection. The FeCrAl on YSZ samples did not exhibit this phenomenon, however a spinel oxide was formed at 1100 C as opposed to alpha-alumina.","Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2016-07-07 without embargo terms","The student, Peter Mouche, accepted the attached license on 2016-04-25 at 16:50.","The student, Peter Mouche, submitted this Thesis for approval on 2016-04-25 at 17:04.","This Thesis was approved for publication on 2016-04-29 at 08:50.","DSpace SAF Submission Ingestion Package generated from Vireo submission #9488 on 2016-07-07 at 13:33:04","Made available in DSpace on 2016-07-07T19:58:01Z (GMT). No. of bitstreams: 2 MOUCHE-THESIS-2016.pdf: 9232383 bytes, checksum: 7a24ea6f443cc1f40d8e83d580172108 (MD5) LICENSE.txt: 4209 bytes, checksum: c03e1855a770fab318387b5de5a7180c (MD5) Previous issue date: 2016-04-29"],"dc:format":["application/pdf"],"dc:identifier":["http://hdl.handle.net/2142/90650"],"dc:language":["en"],"dc:rights":["Copyright 2016 Peter Mouche"],"dc:subject":["Oxidation","Cladding","Nuclear","Accident","Coating","FeCrAl","Steam"],"dc:title":["Steam oxidation of FeCrAl coated Zircaloy-2"],"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":"2026-07-22T22:26:34Z"}