Microstructural analysis of tristructural isotropic particles in high-temperature steam mixed gas atmospheres
•Steam oxidation results of SiC at 1200 °C in 3–21% steam and 0–1% CO.•SiO2 growth were measured in low partial pressure of steam with CO present.•Crystalline SiO2 formed under all conditions.•SiC layer displays microstructural degradation in a high-temperature mixed gas atmosphere. High-temperature...
Gespeichert in:
Veröffentlicht in: | Journal of nuclear materials 2023-06, Vol.579, p.154385, Article 154385 |
---|---|
Hauptverfasser: | , , , , , |
Format: | Artikel |
Sprache: | eng |
Schlagworte: | |
Online-Zugang: | Volltext |
Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
container_end_page | |
---|---|
container_issue | |
container_start_page | 154385 |
container_title | Journal of nuclear materials |
container_volume | 579 |
creator | Montoya, Katherine I. Brigham, Brian A. Helmreich, Grant Werden, Jesse Gerczak, Tyler J. Sooby, Elizabeth S. |
description | •Steam oxidation results of SiC at 1200 °C in 3–21% steam and 0–1% CO.•SiO2 growth were measured in low partial pressure of steam with CO present.•Crystalline SiO2 formed under all conditions.•SiC layer displays microstructural degradation in a high-temperature mixed gas atmosphere.
High-temperature gas-cooled reactors (HTGRs) use tristructural isotropic (TRISO) particles embedded in a graphitic matrix material to form the integral fuel element. Potential off-normal reactor conditions for HTGRs include steam ingress with temperatures above 1,000 °C. Fuel element exposure to steam can cause the graphitic matrix material to evolve, forming an atmosphere composed of oxidants and oxidation products and potentially exposing the TRISO particles to these conditions. Investigating the oxidation response of TRISO particles exposed to a mixed gas atmosphere will provide insight into the stability under off-normal conditions. In this study, surrogate TRISO particles were exposed to high temperatures (T = 1,200 °C) in flowing steam (3% < pH2O < 21%) and CO (pCO < 1%) to determine the oxidation behavior of the SiC layer when exposed to various mixed gas atmospheres. Scanning electron microscopy, x-ray diffraction, and focused ion beam milling was used to determine the impact of CO and steam on the oxidation behavior of the SiC layer. The data presented demonstrates how the SiC layer showed strong oxidation resistance due to limited SiO2 growth and maintained its structural integrity under these off-normal conditions. |
doi_str_mv | 10.1016/j.jnucmat.2023.154385 |
format | Article |
fullrecord | <record><control><sourceid>elsevier_osti_</sourceid><recordid>TN_cdi_osti_scitechconnect_1985403</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0022311523001551</els_id><sourcerecordid>S0022311523001551</sourcerecordid><originalsourceid>FETCH-LOGICAL-c383t-aae35fb3dde4bd2819ef0a72beca970943c2a07f8d14fd5402518161d19ab9a43</originalsourceid><addsrcrecordid>eNqFkMtKAzEUhoMoWKuPIAT3U3OZtJmVSPEGFTe6DqfJmU6GuZGkYt_eGdqFO1dn8V8O_0fILWcLzvjyvl7U3d62kBaCCbngKpdanZEZ1yuZ5VqwczJjTIhMcq4uyVWMNWNMFUzNSPvubehjCnub9gEaCh00h-gj7Uuagv-j-Nin0A_e0gFC8rbBSH1HK7-rsoTtgAFGI9KYEFra-h90dAeRQmr7OFQYMF6TixKaiDenOydfz0-f69ds8_Hytn7cZFZqmTIAlKrcSucw3zqheYElg5XYooVixYpcWgFsVWrH89KpnAnFNV9yxwvYFpDLObk79o7LvInWJ7SV7bsObTK80GNEjiZ1NE0AYsDSDMG3EA6GMzOBNbU5gTUTWHMEO-YejjkcF3x7DNMD7Cw6H6Z-1_t_Gn4BOK-H_A</addsrcrecordid><sourcetype>Open Access Repository</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype></control><display><type>article</type><title>Microstructural analysis of tristructural isotropic particles in high-temperature steam mixed gas atmospheres</title><source>Elsevier ScienceDirect Journals</source><creator>Montoya, Katherine I. ; Brigham, Brian A. ; Helmreich, Grant ; Werden, Jesse ; Gerczak, Tyler J. ; Sooby, Elizabeth S.</creator><creatorcontrib>Montoya, Katherine I. ; Brigham, Brian A. ; Helmreich, Grant ; Werden, Jesse ; Gerczak, Tyler J. ; Sooby, Elizabeth S. ; Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)</creatorcontrib><description>•Steam oxidation results of SiC at 1200 °C in 3–21% steam and 0–1% CO.•SiO2 growth were measured in low partial pressure of steam with CO present.•Crystalline SiO2 formed under all conditions.•SiC layer displays microstructural degradation in a high-temperature mixed gas atmosphere.
High-temperature gas-cooled reactors (HTGRs) use tristructural isotropic (TRISO) particles embedded in a graphitic matrix material to form the integral fuel element. Potential off-normal reactor conditions for HTGRs include steam ingress with temperatures above 1,000 °C. Fuel element exposure to steam can cause the graphitic matrix material to evolve, forming an atmosphere composed of oxidants and oxidation products and potentially exposing the TRISO particles to these conditions. Investigating the oxidation response of TRISO particles exposed to a mixed gas atmosphere will provide insight into the stability under off-normal conditions. In this study, surrogate TRISO particles were exposed to high temperatures (T = 1,200 °C) in flowing steam (3% < pH2O < 21%) and CO (pCO < 1%) to determine the oxidation behavior of the SiC layer when exposed to various mixed gas atmospheres. Scanning electron microscopy, x-ray diffraction, and focused ion beam milling was used to determine the impact of CO and steam on the oxidation behavior of the SiC layer. The data presented demonstrates how the SiC layer showed strong oxidation resistance due to limited SiO2 growth and maintained its structural integrity under these off-normal conditions.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2023.154385</identifier><language>eng</language><publisher>United States: Elsevier B.V</publisher><subject>High-temperature gas reactor ; Ion milling techniques ; Nuclear fuel ; NUCLEAR FUEL CYCLE AND FUEL MATERIALS ; Silicon carbide ; Steam oxidation ; TRISO</subject><ispartof>Journal of nuclear materials, 2023-06, Vol.579, p.154385, Article 154385</ispartof><rights>2023</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c383t-aae35fb3dde4bd2819ef0a72beca970943c2a07f8d14fd5402518161d19ab9a43</citedby><cites>FETCH-LOGICAL-c383t-aae35fb3dde4bd2819ef0a72beca970943c2a07f8d14fd5402518161d19ab9a43</cites><orcidid>0000-0001-5376-3413 ; 0000-0003-2695-5086 ; 0000-0001-6646-0796 ; 0000000326955086 ; 0000000166460796 ; 0000000153763413</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0022311523001551$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>230,314,776,780,881,3536,27903,27904,65309</link.rule.ids><backlink>$$Uhttps://www.osti.gov/servlets/purl/1985403$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Montoya, Katherine I.</creatorcontrib><creatorcontrib>Brigham, Brian A.</creatorcontrib><creatorcontrib>Helmreich, Grant</creatorcontrib><creatorcontrib>Werden, Jesse</creatorcontrib><creatorcontrib>Gerczak, Tyler J.</creatorcontrib><creatorcontrib>Sooby, Elizabeth S.</creatorcontrib><creatorcontrib>Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)</creatorcontrib><title>Microstructural analysis of tristructural isotropic particles in high-temperature steam mixed gas atmospheres</title><title>Journal of nuclear materials</title><description>•Steam oxidation results of SiC at 1200 °C in 3–21% steam and 0–1% CO.•SiO2 growth were measured in low partial pressure of steam with CO present.•Crystalline SiO2 formed under all conditions.•SiC layer displays microstructural degradation in a high-temperature mixed gas atmosphere.
High-temperature gas-cooled reactors (HTGRs) use tristructural isotropic (TRISO) particles embedded in a graphitic matrix material to form the integral fuel element. Potential off-normal reactor conditions for HTGRs include steam ingress with temperatures above 1,000 °C. Fuel element exposure to steam can cause the graphitic matrix material to evolve, forming an atmosphere composed of oxidants and oxidation products and potentially exposing the TRISO particles to these conditions. Investigating the oxidation response of TRISO particles exposed to a mixed gas atmosphere will provide insight into the stability under off-normal conditions. In this study, surrogate TRISO particles were exposed to high temperatures (T = 1,200 °C) in flowing steam (3% < pH2O < 21%) and CO (pCO < 1%) to determine the oxidation behavior of the SiC layer when exposed to various mixed gas atmospheres. Scanning electron microscopy, x-ray diffraction, and focused ion beam milling was used to determine the impact of CO and steam on the oxidation behavior of the SiC layer. The data presented demonstrates how the SiC layer showed strong oxidation resistance due to limited SiO2 growth and maintained its structural integrity under these off-normal conditions.</description><subject>High-temperature gas reactor</subject><subject>Ion milling techniques</subject><subject>Nuclear fuel</subject><subject>NUCLEAR FUEL CYCLE AND FUEL MATERIALS</subject><subject>Silicon carbide</subject><subject>Steam oxidation</subject><subject>TRISO</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2023</creationdate><recordtype>article</recordtype><recordid>eNqFkMtKAzEUhoMoWKuPIAT3U3OZtJmVSPEGFTe6DqfJmU6GuZGkYt_eGdqFO1dn8V8O_0fILWcLzvjyvl7U3d62kBaCCbngKpdanZEZ1yuZ5VqwczJjTIhMcq4uyVWMNWNMFUzNSPvubehjCnub9gEaCh00h-gj7Uuagv-j-Nin0A_e0gFC8rbBSH1HK7-rsoTtgAFGI9KYEFra-h90dAeRQmr7OFQYMF6TixKaiDenOydfz0-f69ds8_Hytn7cZFZqmTIAlKrcSucw3zqheYElg5XYooVixYpcWgFsVWrH89KpnAnFNV9yxwvYFpDLObk79o7LvInWJ7SV7bsObTK80GNEjiZ1NE0AYsDSDMG3EA6GMzOBNbU5gTUTWHMEO-YejjkcF3x7DNMD7Cw6H6Z-1_t_Gn4BOK-H_A</recordid><startdate>20230601</startdate><enddate>20230601</enddate><creator>Montoya, Katherine I.</creator><creator>Brigham, Brian A.</creator><creator>Helmreich, Grant</creator><creator>Werden, Jesse</creator><creator>Gerczak, Tyler J.</creator><creator>Sooby, Elizabeth S.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>AAYXX</scope><scope>CITATION</scope><scope>OIOZB</scope><scope>OTOTI</scope><orcidid>https://orcid.org/0000-0001-5376-3413</orcidid><orcidid>https://orcid.org/0000-0003-2695-5086</orcidid><orcidid>https://orcid.org/0000-0001-6646-0796</orcidid><orcidid>https://orcid.org/0000000326955086</orcidid><orcidid>https://orcid.org/0000000166460796</orcidid><orcidid>https://orcid.org/0000000153763413</orcidid></search><sort><creationdate>20230601</creationdate><title>Microstructural analysis of tristructural isotropic particles in high-temperature steam mixed gas atmospheres</title><author>Montoya, Katherine I. ; Brigham, Brian A. ; Helmreich, Grant ; Werden, Jesse ; Gerczak, Tyler J. ; Sooby, Elizabeth S.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c383t-aae35fb3dde4bd2819ef0a72beca970943c2a07f8d14fd5402518161d19ab9a43</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2023</creationdate><topic>High-temperature gas reactor</topic><topic>Ion milling techniques</topic><topic>Nuclear fuel</topic><topic>NUCLEAR FUEL CYCLE AND FUEL MATERIALS</topic><topic>Silicon carbide</topic><topic>Steam oxidation</topic><topic>TRISO</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Montoya, Katherine I.</creatorcontrib><creatorcontrib>Brigham, Brian A.</creatorcontrib><creatorcontrib>Helmreich, Grant</creatorcontrib><creatorcontrib>Werden, Jesse</creatorcontrib><creatorcontrib>Gerczak, Tyler J.</creatorcontrib><creatorcontrib>Sooby, Elizabeth S.</creatorcontrib><creatorcontrib>Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)</creatorcontrib><collection>CrossRef</collection><collection>OSTI.GOV - Hybrid</collection><collection>OSTI.GOV</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Montoya, Katherine I.</au><au>Brigham, Brian A.</au><au>Helmreich, Grant</au><au>Werden, Jesse</au><au>Gerczak, Tyler J.</au><au>Sooby, Elizabeth S.</au><aucorp>Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Microstructural analysis of tristructural isotropic particles in high-temperature steam mixed gas atmospheres</atitle><jtitle>Journal of nuclear materials</jtitle><date>2023-06-01</date><risdate>2023</risdate><volume>579</volume><spage>154385</spage><pages>154385-</pages><artnum>154385</artnum><issn>0022-3115</issn><eissn>1873-4820</eissn><abstract>•Steam oxidation results of SiC at 1200 °C in 3–21% steam and 0–1% CO.•SiO2 growth were measured in low partial pressure of steam with CO present.•Crystalline SiO2 formed under all conditions.•SiC layer displays microstructural degradation in a high-temperature mixed gas atmosphere.
High-temperature gas-cooled reactors (HTGRs) use tristructural isotropic (TRISO) particles embedded in a graphitic matrix material to form the integral fuel element. Potential off-normal reactor conditions for HTGRs include steam ingress with temperatures above 1,000 °C. Fuel element exposure to steam can cause the graphitic matrix material to evolve, forming an atmosphere composed of oxidants and oxidation products and potentially exposing the TRISO particles to these conditions. Investigating the oxidation response of TRISO particles exposed to a mixed gas atmosphere will provide insight into the stability under off-normal conditions. In this study, surrogate TRISO particles were exposed to high temperatures (T = 1,200 °C) in flowing steam (3% < pH2O < 21%) and CO (pCO < 1%) to determine the oxidation behavior of the SiC layer when exposed to various mixed gas atmospheres. Scanning electron microscopy, x-ray diffraction, and focused ion beam milling was used to determine the impact of CO and steam on the oxidation behavior of the SiC layer. The data presented demonstrates how the SiC layer showed strong oxidation resistance due to limited SiO2 growth and maintained its structural integrity under these off-normal conditions.</abstract><cop>United States</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2023.154385</doi><orcidid>https://orcid.org/0000-0001-5376-3413</orcidid><orcidid>https://orcid.org/0000-0003-2695-5086</orcidid><orcidid>https://orcid.org/0000-0001-6646-0796</orcidid><orcidid>https://orcid.org/0000000326955086</orcidid><orcidid>https://orcid.org/0000000166460796</orcidid><orcidid>https://orcid.org/0000000153763413</orcidid><oa>free_for_read</oa></addata></record> |
fulltext | fulltext |
identifier | ISSN: 0022-3115 |
ispartof | Journal of nuclear materials, 2023-06, Vol.579, p.154385, Article 154385 |
issn | 0022-3115 1873-4820 |
language | eng |
recordid | cdi_osti_scitechconnect_1985403 |
source | Elsevier ScienceDirect Journals |
subjects | High-temperature gas reactor Ion milling techniques Nuclear fuel NUCLEAR FUEL CYCLE AND FUEL MATERIALS Silicon carbide Steam oxidation TRISO |
title | Microstructural analysis of tristructural isotropic particles in high-temperature steam mixed gas atmospheres |
url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-25T11%3A12%3A15IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-elsevier_osti_&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Microstructural%20analysis%20of%20tristructural%20isotropic%20particles%20in%20high-temperature%20steam%20mixed%20gas%20atmospheres&rft.jtitle=Journal%20of%20nuclear%20materials&rft.au=Montoya,%20Katherine%20I.&rft.aucorp=Oak%20Ridge%20National%20Laboratory%20(ORNL),%20Oak%20Ridge,%20TN%20(United%20States)&rft.date=2023-06-01&rft.volume=579&rft.spage=154385&rft.pages=154385-&rft.artnum=154385&rft.issn=0022-3115&rft.eissn=1873-4820&rft_id=info:doi/10.1016/j.jnucmat.2023.154385&rft_dat=%3Celsevier_osti_%3ES0022311523001551%3C/elsevier_osti_%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_id=info:pmid/&rft_els_id=S0022311523001551&rfr_iscdi=true |