Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor
In order to investigate the effect of americium addition in MOX fuel on the irradiation behavior, the ‘Am-1’ program is being conducted in the experimental fast reactor Joyo. The Am-1 program consists of two short-term irradiation tests of 10min and 24h irradiations and a steady-state irradiation te...
Gespeichert in:
| Veröffentlicht in: | Journal of nuclear materials 2009-03, Vol.385 (2), p.407-412 |
|---|---|
| Hauptverfasser: | , , , , , , , |
| Format: | Artikel |
| Sprache: | eng |
| Schlagworte: | |
| Online-Zugang: | Volltext |
| Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
| container_end_page | 412 |
|---|---|
| container_issue | 2 |
| container_start_page | 407 |
| container_title | Journal of nuclear materials |
| container_volume | 385 |
| creator | Tanaka, Kosuke Miwa, Shuhei Sato, Isamu Hirosawa, Takashi Obayashi, Hiroshi Koyama, Shin-ichi Yoshimochi, Hiroshi Tanaka, Kenya |
| description | In order to investigate the effect of americium addition in MOX fuel on the irradiation behavior, the ‘Am-1’ program is being conducted in the experimental fast reactor Joyo. The Am-1 program consists of two short-term irradiation tests of 10min and 24h irradiations and a steady-state irradiation test. The short-term irradiation tests were successfully completed and the post irradiation examinations (PIEs) are in progress. This paper reports on the results of PIEs for Am-containing MOX fuel irradiated for 10min. MOX fuel pellets containing 3% or 5% Am were fabricated in a shielded air-tight hot cell using a remote handling technique. The oxygen to metal ratio (O/M) of these fuel pellets was 1.98. They were irradiated at peak linear heating rate of about 43kWm−1. Focus was being placed on migration behavior of Am during the irradiation. The ceramography results showed that structural changes such as lenticular pores and a central void occurred early, within the brief 10min of irradiation. The results of electron probe microanalysis revealed that the concentration of Am increased in the vicinity of the central void. |
| doi_str_mv | 10.1016/j.jnucmat.2008.12.028 |
| format | Article |
| fullrecord | <record><control><sourceid>proquest_cross</sourceid><recordid>TN_cdi_proquest_miscellaneous_33771752</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0022311508007472</els_id><sourcerecordid>20540808</sourcerecordid><originalsourceid>FETCH-LOGICAL-c401t-912668f50376713245c2676bb43db70d09e662725d6c756e24ed175a755dcc843</originalsourceid><addsrcrecordid>eNqFkcuOEzEQRVsIJMLAJyB5A7sOZXfb7qwQGvGSZsQG1pZjV0NF3XbwAw2_wtfiTKLZzqpK5XOrrHu77jWHLQeu3h22h1DdastWAExbLrYgpifdhk966MdJwNNuAyBEP3Aun3cvcj4AgNyB3HT_bsmlmEuqrtSEzAbPcMEVQ7EL89ReaF8LxcDizOyKiRzVtXexARQo_GQ12dBG7LjUEu-7le7Qs3hHHtlccWE1eEzMsvwrptIXTCujlKwne7-5YC6MQgNm27qE1pWYXnbPZrtkfHWpV92PTx-_X3_pb759_nr94aZ3I_DS77hQapolDFppPohROqG02u_Hwe81eNihUkIL6ZXTUqEY0XMtrZbSOzeNw1X39rz3mOLv2r5iVsoOl8UGjDWbYdC6CcSjoAA5wgRTA-UZPFmbE87mmGi16a_hYE6RmYO5RGZOkRkuTIus6d5cDtjs7DI3Yx3lB7Hgg1J62DXu_ZnDZssfwmSyIwwOPSV0xfhIj1z6D8VzsnM</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>20540808</pqid></control><display><type>article</type><title>Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor</title><source>Access via ScienceDirect (Elsevier)</source><creator>Tanaka, Kosuke ; Miwa, Shuhei ; Sato, Isamu ; Hirosawa, Takashi ; Obayashi, Hiroshi ; Koyama, Shin-ichi ; Yoshimochi, Hiroshi ; Tanaka, Kenya</creator><creatorcontrib>Tanaka, Kosuke ; Miwa, Shuhei ; Sato, Isamu ; Hirosawa, Takashi ; Obayashi, Hiroshi ; Koyama, Shin-ichi ; Yoshimochi, Hiroshi ; Tanaka, Kenya</creatorcontrib><description>In order to investigate the effect of americium addition in MOX fuel on the irradiation behavior, the ‘Am-1’ program is being conducted in the experimental fast reactor Joyo. The Am-1 program consists of two short-term irradiation tests of 10min and 24h irradiations and a steady-state irradiation test. The short-term irradiation tests were successfully completed and the post irradiation examinations (PIEs) are in progress. This paper reports on the results of PIEs for Am-containing MOX fuel irradiated for 10min. MOX fuel pellets containing 3% or 5% Am were fabricated in a shielded air-tight hot cell using a remote handling technique. The oxygen to metal ratio (O/M) of these fuel pellets was 1.98. They were irradiated at peak linear heating rate of about 43kWm−1. Focus was being placed on migration behavior of Am during the irradiation. The ceramography results showed that structural changes such as lenticular pores and a central void occurred early, within the brief 10min of irradiation. The results of electron probe microanalysis revealed that the concentration of Am increased in the vicinity of the central void.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2008.12.028</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Fuels ; Installations for energy generation and conversion: thermal and electrical energy ; Nuclear fuels ; Preparation and processing of nuclear fuels</subject><ispartof>Journal of nuclear materials, 2009-03, Vol.385 (2), p.407-412</ispartof><rights>2008 Elsevier B.V.</rights><rights>2009 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c401t-912668f50376713245c2676bb43db70d09e662725d6c756e24ed175a755dcc843</citedby><cites>FETCH-LOGICAL-c401t-912668f50376713245c2676bb43db70d09e662725d6c756e24ed175a755dcc843</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.jnucmat.2008.12.028$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>309,310,314,780,784,789,790,3550,23930,23931,25140,27924,27925,45995</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=21366739$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Tanaka, Kosuke</creatorcontrib><creatorcontrib>Miwa, Shuhei</creatorcontrib><creatorcontrib>Sato, Isamu</creatorcontrib><creatorcontrib>Hirosawa, Takashi</creatorcontrib><creatorcontrib>Obayashi, Hiroshi</creatorcontrib><creatorcontrib>Koyama, Shin-ichi</creatorcontrib><creatorcontrib>Yoshimochi, Hiroshi</creatorcontrib><creatorcontrib>Tanaka, Kenya</creatorcontrib><title>Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor</title><title>Journal of nuclear materials</title><description>In order to investigate the effect of americium addition in MOX fuel on the irradiation behavior, the ‘Am-1’ program is being conducted in the experimental fast reactor Joyo. The Am-1 program consists of two short-term irradiation tests of 10min and 24h irradiations and a steady-state irradiation test. The short-term irradiation tests were successfully completed and the post irradiation examinations (PIEs) are in progress. This paper reports on the results of PIEs for Am-containing MOX fuel irradiated for 10min. MOX fuel pellets containing 3% or 5% Am were fabricated in a shielded air-tight hot cell using a remote handling technique. The oxygen to metal ratio (O/M) of these fuel pellets was 1.98. They were irradiated at peak linear heating rate of about 43kWm−1. Focus was being placed on migration behavior of Am during the irradiation. The ceramography results showed that structural changes such as lenticular pores and a central void occurred early, within the brief 10min of irradiation. The results of electron probe microanalysis revealed that the concentration of Am increased in the vicinity of the central void.</description><subject>Applied sciences</subject><subject>Controled nuclear fusion plants</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Fuels</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Nuclear fuels</subject><subject>Preparation and processing of nuclear fuels</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2009</creationdate><recordtype>article</recordtype><recordid>eNqFkcuOEzEQRVsIJMLAJyB5A7sOZXfb7qwQGvGSZsQG1pZjV0NF3XbwAw2_wtfiTKLZzqpK5XOrrHu77jWHLQeu3h22h1DdastWAExbLrYgpifdhk966MdJwNNuAyBEP3Aun3cvcj4AgNyB3HT_bsmlmEuqrtSEzAbPcMEVQ7EL89ReaF8LxcDizOyKiRzVtXexARQo_GQ12dBG7LjUEu-7le7Qs3hHHtlccWE1eEzMsvwrptIXTCujlKwne7-5YC6MQgNm27qE1pWYXnbPZrtkfHWpV92PTx-_X3_pb759_nr94aZ3I_DS77hQapolDFppPohROqG02u_Hwe81eNihUkIL6ZXTUqEY0XMtrZbSOzeNw1X39rz3mOLv2r5iVsoOl8UGjDWbYdC6CcSjoAA5wgRTA-UZPFmbE87mmGi16a_hYE6RmYO5RGZOkRkuTIus6d5cDtjs7DI3Yx3lB7Hgg1J62DXu_ZnDZssfwmSyIwwOPSV0xfhIj1z6D8VzsnM</recordid><startdate>20090331</startdate><enddate>20090331</enddate><creator>Tanaka, Kosuke</creator><creator>Miwa, Shuhei</creator><creator>Sato, Isamu</creator><creator>Hirosawa, Takashi</creator><creator>Obayashi, Hiroshi</creator><creator>Koyama, Shin-ichi</creator><creator>Yoshimochi, Hiroshi</creator><creator>Tanaka, Kenya</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7ST</scope><scope>C1K</scope><scope>SOI</scope><scope>7SR</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>JG9</scope><scope>L7M</scope></search><sort><creationdate>20090331</creationdate><title>Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor</title><author>Tanaka, Kosuke ; Miwa, Shuhei ; Sato, Isamu ; Hirosawa, Takashi ; Obayashi, Hiroshi ; Koyama, Shin-ichi ; Yoshimochi, Hiroshi ; Tanaka, Kenya</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c401t-912668f50376713245c2676bb43db70d09e662725d6c756e24ed175a755dcc843</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2009</creationdate><topic>Applied sciences</topic><topic>Controled nuclear fusion plants</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Fuels</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Nuclear fuels</topic><topic>Preparation and processing of nuclear fuels</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Tanaka, Kosuke</creatorcontrib><creatorcontrib>Miwa, Shuhei</creatorcontrib><creatorcontrib>Sato, Isamu</creatorcontrib><creatorcontrib>Hirosawa, Takashi</creatorcontrib><creatorcontrib>Obayashi, Hiroshi</creatorcontrib><creatorcontrib>Koyama, Shin-ichi</creatorcontrib><creatorcontrib>Yoshimochi, Hiroshi</creatorcontrib><creatorcontrib>Tanaka, Kenya</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Environment Abstracts</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Environment Abstracts</collection><collection>Engineered Materials Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Tanaka, Kosuke</au><au>Miwa, Shuhei</au><au>Sato, Isamu</au><au>Hirosawa, Takashi</au><au>Obayashi, Hiroshi</au><au>Koyama, Shin-ichi</au><au>Yoshimochi, Hiroshi</au><au>Tanaka, Kenya</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor</atitle><jtitle>Journal of nuclear materials</jtitle><date>2009-03-31</date><risdate>2009</risdate><volume>385</volume><issue>2</issue><spage>407</spage><epage>412</epage><pages>407-412</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>In order to investigate the effect of americium addition in MOX fuel on the irradiation behavior, the ‘Am-1’ program is being conducted in the experimental fast reactor Joyo. The Am-1 program consists of two short-term irradiation tests of 10min and 24h irradiations and a steady-state irradiation test. The short-term irradiation tests were successfully completed and the post irradiation examinations (PIEs) are in progress. This paper reports on the results of PIEs for Am-containing MOX fuel irradiated for 10min. MOX fuel pellets containing 3% or 5% Am were fabricated in a shielded air-tight hot cell using a remote handling technique. The oxygen to metal ratio (O/M) of these fuel pellets was 1.98. They were irradiated at peak linear heating rate of about 43kWm−1. Focus was being placed on migration behavior of Am during the irradiation. The ceramography results showed that structural changes such as lenticular pores and a central void occurred early, within the brief 10min of irradiation. The results of electron probe microanalysis revealed that the concentration of Am increased in the vicinity of the central void.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2008.12.028</doi><tpages>6</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0022-3115 |
| ispartof | Journal of nuclear materials, 2009-03, Vol.385 (2), p.407-412 |
| issn | 0022-3115 1873-4820 |
| language | eng |
| recordid | cdi_proquest_miscellaneous_33771752 |
| source | Access via ScienceDirect (Elsevier) |
| subjects | Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fuels Installations for energy generation and conversion: thermal and electrical energy Nuclear fuels Preparation and processing of nuclear fuels |
| title | Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor |
| url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-12-29T13%3A07%3A25IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_cross&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Microstructure%20and%20elemental%20distribution%20of%20americium-containing%20uranium%20plutonium%20mixed%20oxide%20fuel%20under%20a%20short-term%20irradiation%20test%20in%20a%20fast%20reactor&rft.jtitle=Journal%20of%20nuclear%20materials&rft.au=Tanaka,%20Kosuke&rft.date=2009-03-31&rft.volume=385&rft.issue=2&rft.spage=407&rft.epage=412&rft.pages=407-412&rft.issn=0022-3115&rft.eissn=1873-4820&rft.coden=JNUMAM&rft_id=info:doi/10.1016/j.jnucmat.2008.12.028&rft_dat=%3Cproquest_cross%3E20540808%3C/proquest_cross%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=20540808&rft_id=info:pmid/&rft_els_id=S0022311508007472&rfr_iscdi=true |