Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure
In the case of a contact between groundwater and Fe-based spent fuel disposal containers in a repository large amounts of hydrogen will be produced by the corrosion of iron, which may result in significant hydrogen pressures. To quantify to what extent the hydrogen overpressure may counteract radiol...
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| Veröffentlicht in: | Journal of nuclear materials 2005-11, Vol.346 (1), p.24-31 |
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| container_title | Journal of nuclear materials |
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| creator | Loida, Andreas Metz, Volker Kienzler, Bernhard Geckeis, Horst |
| description | In the case of a contact between groundwater and Fe-based spent fuel disposal containers in a repository large amounts of hydrogen will be produced by the corrosion of iron, which may result in significant hydrogen pressures. To quantify to what extent the hydrogen overpressure may counteract radiolysis enhanced matrix dissolution, related experimental work has been performed. High burnup spent fuel was corroded in 5.6
mol (kg H
2O)
−1 NaCl solution applying H
2 overpressures (experimental set 1) |
| doi_str_mv | 10.1016/j.jnucmat.2005.05.020 |
| format | Article |
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mol (kg H
2O)
−1 NaCl solution applying H
2 overpressures (experimental set 1) <0.17
bar by radiolysis, (experimental set 2) 2.8
bar by Fe corrosion, (experimental set 3) 3.2
bar by external H
2 gas. In the absence of Fe (experimental set 3) the UO
2 matrix dissolution rate decreased by a factor of about 10. In this test the concentrations of U, Np, Tc in solution were found to be decreasing by at least two orders of magnitude, and ranging within the same level as in the presence of Fe powder (experimental set 2). However, Pu and Am concentrations (experimental set 3) were less affected, due to the high sorption capacity for these radioelements onto Fe corrosion products.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2005.05.020</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Energy ; Exact sciences and technology ; Fuels ; Nuclear fuels ; Preparation and processing of nuclear fuels</subject><ispartof>Journal of nuclear materials, 2005-11, Vol.346 (1), p.24-31</ispartof><rights>2005 Elsevier B.V.</rights><rights>2006 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c370t-d768e19ccb7e87b873a9618017389f06a98372f847424de9debcba1988ca65073</citedby><cites>FETCH-LOGICAL-c370t-d768e19ccb7e87b873a9618017389f06a98372f847424de9debcba1988ca65073</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0022311505003156$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>309,310,314,776,780,785,786,3537,23909,23910,25118,27901,27902,65306</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=17303274$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Loida, Andreas</creatorcontrib><creatorcontrib>Metz, Volker</creatorcontrib><creatorcontrib>Kienzler, Bernhard</creatorcontrib><creatorcontrib>Geckeis, Horst</creatorcontrib><title>Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure</title><title>Journal of nuclear materials</title><description>In the case of a contact between groundwater and Fe-based spent fuel disposal containers in a repository large amounts of hydrogen will be produced by the corrosion of iron, which may result in significant hydrogen pressures. To quantify to what extent the hydrogen overpressure may counteract radiolysis enhanced matrix dissolution, related experimental work has been performed. High burnup spent fuel was corroded in 5.6
mol (kg H
2O)
−1 NaCl solution applying H
2 overpressures (experimental set 1) <0.17
bar by radiolysis, (experimental set 2) 2.8
bar by Fe corrosion, (experimental set 3) 3.2
bar by external H
2 gas. In the absence of Fe (experimental set 3) the UO
2 matrix dissolution rate decreased by a factor of about 10. In this test the concentrations of U, Np, Tc in solution were found to be decreasing by at least two orders of magnitude, and ranging within the same level as in the presence of Fe powder (experimental set 2). However, Pu and Am concentrations (experimental set 3) were less affected, due to the high sorption capacity for these radioelements onto Fe corrosion products.</description><subject>Applied sciences</subject><subject>Energy</subject><subject>Exact sciences and technology</subject><subject>Fuels</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>2005</creationdate><recordtype>article</recordtype><recordid>eNqFkFuLFDEQhYMoOK7-BCEv-tazlfQl6SeRxcvCgiD6HNJJ9UyGnqStdC_uvzftDPgoFBSVfKeKcxh7K2AvQHS3p_0pru5sl70EaPdbSXjGdkKrumq0hOdsByBlVQvRvmSvcj5BAXtod-z3d-tDKvIpeOSEE9qMfKR05sdwOPJhpbjOPM8YFz6uOHG_UogH7hJRykXKQ-TZTgsfyjtu03JEPhNmjA55GvnxyVM6YOTpEWn7yCvha_ZitFPGN9d-w35-_vTj7mv18O3L_d3Hh8rVCpbKq06j6J0bFGo1FEe274QGoWrdj9DZXtdKjrpRjWw89h4HN1jRa-1s14Kqb9j7y96Z0q8V82LOITucJhsxrdnIvu2aRkIB2wvoiq9MOJqZwtnSkxFgtpzNyVxzNlvOZqu_unfXAzY7O41kowv5n1jVUEvVFO7DhcPi9jEgmezCFpEPhG4xPoX_XPoDdkOYbA</recordid><startdate>20051101</startdate><enddate>20051101</enddate><creator>Loida, Andreas</creator><creator>Metz, Volker</creator><creator>Kienzler, Bernhard</creator><creator>Geckeis, Horst</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SE</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>20051101</creationdate><title>Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure</title><author>Loida, Andreas ; Metz, Volker ; Kienzler, Bernhard ; Geckeis, Horst</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c370t-d768e19ccb7e87b873a9618017389f06a98372f847424de9debcba1988ca65073</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2005</creationdate><topic>Applied sciences</topic><topic>Energy</topic><topic>Exact sciences and technology</topic><topic>Fuels</topic><topic>Nuclear fuels</topic><topic>Preparation and processing of nuclear fuels</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Loida, Andreas</creatorcontrib><creatorcontrib>Metz, Volker</creatorcontrib><creatorcontrib>Kienzler, Bernhard</creatorcontrib><creatorcontrib>Geckeis, Horst</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Corrosion 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>Loida, Andreas</au><au>Metz, Volker</au><au>Kienzler, Bernhard</au><au>Geckeis, Horst</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure</atitle><jtitle>Journal of nuclear materials</jtitle><date>2005-11-01</date><risdate>2005</risdate><volume>346</volume><issue>1</issue><spage>24</spage><epage>31</epage><pages>24-31</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>In the case of a contact between groundwater and Fe-based spent fuel disposal containers in a repository large amounts of hydrogen will be produced by the corrosion of iron, which may result in significant hydrogen pressures. To quantify to what extent the hydrogen overpressure may counteract radiolysis enhanced matrix dissolution, related experimental work has been performed. High burnup spent fuel was corroded in 5.6
mol (kg H
2O)
−1 NaCl solution applying H
2 overpressures (experimental set 1) <0.17
bar by radiolysis, (experimental set 2) 2.8
bar by Fe corrosion, (experimental set 3) 3.2
bar by external H
2 gas. In the absence of Fe (experimental set 3) the UO
2 matrix dissolution rate decreased by a factor of about 10. In this test the concentrations of U, Np, Tc in solution were found to be decreasing by at least two orders of magnitude, and ranging within the same level as in the presence of Fe powder (experimental set 2). However, Pu and Am concentrations (experimental set 3) were less affected, due to the high sorption capacity for these radioelements onto Fe corrosion products.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2005.05.020</doi><tpages>8</tpages></addata></record> |
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| language | eng |
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| source | Elsevier ScienceDirect Journals |
| subjects | Applied sciences Energy Exact sciences and technology Fuels Nuclear fuels Preparation and processing of nuclear fuels |
| title | Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure |
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