Development of fuel-model interfaces: Investigations by XPS, TEM, SEM and AFM
The presented work aims to reproducibly prepare UO 2–Pd thin film model systems for spent nuclear fuel in order to further investigate surface reactions of these films under relevant redox conditions. The sputter co-deposition of U and Pd (fission product) in the presence of O 2 results in the homog...
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Veröffentlicht in: | Journal of nuclear materials 2009-03, Vol.385 (1), p.208-211 |
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container_title | Journal of nuclear materials |
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creator | Stumpf, S. Seibert, A. Gouder, T. Huber, F. Wiss, T. Römer, J. |
description | The presented work aims to reproducibly prepare UO
2–Pd thin film model systems for spent nuclear fuel in order to further investigate surface reactions of these films under relevant redox conditions. The sputter co-deposition of U and Pd (fission product) in the presence of O
2 results in the homogenous distribution of Pd in a crystalline UO
2 matrix. Heating the films causes the diffusion of film components. Hereby, the formation of ε-particles has to be clarified. First electrochemical studies show the influence of the nobel metal Pd on the redox behaviour of UO
2. With increasing Pd concentration the matrix dissolution is decreased. However, we could demonstrate that blocked oxidation processes are of temporary nature. The passivation of the Pd reactive sites with increasing number of cycles finally induces the approximation of the mixed system to the redox behaviour of the pure UO
2 system. |
doi_str_mv | 10.1016/j.jnucmat.2008.08.061 |
format | Article |
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2–Pd thin film model systems for spent nuclear fuel in order to further investigate surface reactions of these films under relevant redox conditions. The sputter co-deposition of U and Pd (fission product) in the presence of O
2 results in the homogenous distribution of Pd in a crystalline UO
2 matrix. Heating the films causes the diffusion of film components. Hereby, the formation of ε-particles has to be clarified. First electrochemical studies show the influence of the nobel metal Pd on the redox behaviour of UO
2. With increasing Pd concentration the matrix dissolution is decreased. However, we could demonstrate that blocked oxidation processes are of temporary nature. The passivation of the Pd reactive sites with increasing number of cycles finally induces the approximation of the mixed system to the redox behaviour of the pure UO
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2–Pd thin film model systems for spent nuclear fuel in order to further investigate surface reactions of these films under relevant redox conditions. The sputter co-deposition of U and Pd (fission product) in the presence of O
2 results in the homogenous distribution of Pd in a crystalline UO
2 matrix. Heating the films causes the diffusion of film components. Hereby, the formation of ε-particles has to be clarified. First electrochemical studies show the influence of the nobel metal Pd on the redox behaviour of UO
2. With increasing Pd concentration the matrix dissolution is decreased. However, we could demonstrate that blocked oxidation processes are of temporary nature. The passivation of the Pd reactive sites with increasing number of cycles finally induces the approximation of the mixed system to the redox behaviour of the pure UO
2 system.</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>eNqFkE1rGzEQhkVoIW7SnxDQpT15nRmttB-9lJA6HxDTQhLITcjaUZDZ1brSriH_vmtsejUMzOV55x0exq4QFghYXG8WmzDazgwLAVAt9lPgGZthVeaZrAR8YjMAIbIcUZ2zLyltAEDVoGZs9Yt21PbbjsLAe8fdSG3W9Q213IeBojOW0g_-GHaUBv9uBt-HxNcf_O3P85y_LFdz_rxccRMafnO3umSfnWkTfT3uC_Z6t3y5fcieft8_3t48ZVYCDplTlSmllUaRrIWTUDlQSq4bVwgq1RrRiUIaC6WdwLoAWVslSVVFYUpVivyCfT_c3cb-7zh9pjufLLWtCdSPSed5iShFdRIUoCTWqCZQHUAb-5QiOb2NvjPxQyPovWW90UfLem9Z76fAKfftWGCSNa2LJlif_ocF5nklQU7czwNHk5adp6iT9RQsNT6SHXTT-xNN_wBadZKe</recordid><startdate>20090315</startdate><enddate>20090315</enddate><creator>Stumpf, S.</creator><creator>Seibert, A.</creator><creator>Gouder, T.</creator><creator>Huber, F.</creator><creator>Wiss, T.</creator><creator>Römer, J.</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>20090315</creationdate><title>Development of fuel-model interfaces: Investigations by XPS, TEM, SEM and AFM</title><author>Stumpf, S. ; Seibert, A. ; Gouder, T. ; Huber, F. ; Wiss, T. ; Römer, J.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c401t-f58a74c4a5e492f408f0554bdf62e75b11f264ac07c8a796049c54e5866a75723</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>Stumpf, S.</creatorcontrib><creatorcontrib>Seibert, A.</creatorcontrib><creatorcontrib>Gouder, T.</creatorcontrib><creatorcontrib>Huber, F.</creatorcontrib><creatorcontrib>Wiss, T.</creatorcontrib><creatorcontrib>Römer, J.</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>Stumpf, S.</au><au>Seibert, A.</au><au>Gouder, T.</au><au>Huber, F.</au><au>Wiss, T.</au><au>Römer, J.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Development of fuel-model interfaces: Investigations by XPS, TEM, SEM and AFM</atitle><jtitle>Journal of nuclear materials</jtitle><date>2009-03-15</date><risdate>2009</risdate><volume>385</volume><issue>1</issue><spage>208</spage><epage>211</epage><pages>208-211</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>The presented work aims to reproducibly prepare UO
2–Pd thin film model systems for spent nuclear fuel in order to further investigate surface reactions of these films under relevant redox conditions. The sputter co-deposition of U and Pd (fission product) in the presence of O
2 results in the homogenous distribution of Pd in a crystalline UO
2 matrix. Heating the films causes the diffusion of film components. Hereby, the formation of ε-particles has to be clarified. First electrochemical studies show the influence of the nobel metal Pd on the redox behaviour of UO
2. With increasing Pd concentration the matrix dissolution is decreased. However, we could demonstrate that blocked oxidation processes are of temporary nature. The passivation of the Pd reactive sites with increasing number of cycles finally induces the approximation of the mixed system to the redox behaviour of the pure UO
2 system.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2008.08.061</doi><tpages>4</tpages></addata></record> |
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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 | Development of fuel-model interfaces: Investigations by XPS, TEM, SEM and AFM |
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