Experimental determination of U0O(cr) dissolution kinetics: Effects of solution saturation state and pH
To evaluate the release of uranium from natural ore deposits, spent nuclear fuel repositories, and REDOX permeable reactive barriers (PRB), knowledge of the fundamental reaction kinetics associated with the dissolution of uranium dioxide is necessary. Dissolution of crystalline uranium (IV) dioxide...
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Veröffentlicht in: | Journal of nuclear materials 2005-10, Vol.345 (2-3), p.206-218 |
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description | To evaluate the release of uranium from natural ore deposits, spent nuclear fuel repositories, and REDOX permeable reactive barriers (PRB), knowledge of the fundamental reaction kinetics associated with the dissolution of uranium dioxide is necessary. Dissolution of crystalline uranium (IV) dioxide under environmental conditions has been studied for four decades but a cardinal gap in the published literature is the effect of pH and solution saturation state on UO2(cr) dissolution. To resolve inconsistencies, UO2 dissolution experiments have been conducted under oxic conditions using the single-pass flow-through system. Experiments were conducted as a function of total dissolved carbonate ([CO3-3]T) from 0.001 to 0.1 M; pH from 7.5 to 11.1; ratio of flow-through rate (q) to specific surface area (S), constant ionic strength (I) = 0.1 M, and temperatures (T) from 23 to 60 DGC utilizing both powder and monolithic specimens. The results show that UO2 dissolution varies as a function of the ratio q/S and temperature. At values of log10q/S > -7.0, UO2 dissolution becomes invariant with respect to q/S, which can be interpreted as evidence for dissolution at the forward rate of reaction. The data collected in these experiments show the rate of UO2 dissolution increased by an order of magnitude with a 30 DGC increase in temperature. The results also show the overall dissolution rate increases with an increase in pH and decreases as the dissolved uranium concentration approaches saturation with respect to secondary reaction products. Thus, as the value of the reaction quotient, Q, approaches equilibrium, K, (with respect to a potential secondary phase) the dissolution rate decreases. This decrease in dissolution rate (r) was also observed when comparing measured UO2 dissolution rates from static tests where r = 1.7 - 0.14 x 10-8 mol M-2 s-1 to the rate for flow-through reactors where r = 3.1 - 1.2 x 10-7 mol m-2 s-1. Thus, using traditional static test methods can result in an underestimation of the true forward rate of UO2(cr) dissolution. These results illustrate the importance of pH, solution saturation state, and the concentration of dissolved carbonate on the release of uranium from UO2 in the natural environment. |
doi_str_mv | 10.1016/j.jnucmat.2005.05.012 |
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Dissolution of crystalline uranium (IV) dioxide under environmental conditions has been studied for four decades but a cardinal gap in the published literature is the effect of pH and solution saturation state on UO2(cr) dissolution. To resolve inconsistencies, UO2 dissolution experiments have been conducted under oxic conditions using the single-pass flow-through system. Experiments were conducted as a function of total dissolved carbonate ([CO3-3]T) from 0.001 to 0.1 M; pH from 7.5 to 11.1; ratio of flow-through rate (q) to specific surface area (S), constant ionic strength (I) = 0.1 M, and temperatures (T) from 23 to 60 DGC utilizing both powder and monolithic specimens. The results show that UO2 dissolution varies as a function of the ratio q/S and temperature. At values of log10q/S > -7.0, UO2 dissolution becomes invariant with respect to q/S, which can be interpreted as evidence for dissolution at the forward rate of reaction. The data collected in these experiments show the rate of UO2 dissolution increased by an order of magnitude with a 30 DGC increase in temperature. The results also show the overall dissolution rate increases with an increase in pH and decreases as the dissolved uranium concentration approaches saturation with respect to secondary reaction products. Thus, as the value of the reaction quotient, Q, approaches equilibrium, K, (with respect to a potential secondary phase) the dissolution rate decreases. This decrease in dissolution rate (r) was also observed when comparing measured UO2 dissolution rates from static tests where r = 1.7 - 0.14 x 10-8 mol M-2 s-1 to the rate for flow-through reactors where r = 3.1 - 1.2 x 10-7 mol m-2 s-1. Thus, using traditional static test methods can result in an underestimation of the true forward rate of UO2(cr) dissolution. These results illustrate the importance of pH, solution saturation state, and the concentration of dissolved carbonate on the release of uranium from UO2 in the natural environment.</description><identifier>ISSN: 0022-3115</identifier><identifier>DOI: 10.1016/j.jnucmat.2005.05.012</identifier><language>eng</language><ispartof>Journal of nuclear materials, 2005-10, Vol.345 (2-3), p.206-218</ispartof><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,776,780,27901,27902</link.rule.ids></links><search><creatorcontrib>Pierce, E M</creatorcontrib><creatorcontrib>Icenhower, J P</creatorcontrib><creatorcontrib>Serne, R J</creatorcontrib><creatorcontrib>Catalano, J G</creatorcontrib><title>Experimental determination of U0O(cr) dissolution kinetics: Effects of solution saturation state and pH</title><title>Journal of nuclear materials</title><description>To evaluate the release of uranium from natural ore deposits, spent nuclear fuel repositories, and REDOX permeable reactive barriers (PRB), knowledge of the fundamental reaction kinetics associated with the dissolution of uranium dioxide is necessary. Dissolution of crystalline uranium (IV) dioxide under environmental conditions has been studied for four decades but a cardinal gap in the published literature is the effect of pH and solution saturation state on UO2(cr) dissolution. To resolve inconsistencies, UO2 dissolution experiments have been conducted under oxic conditions using the single-pass flow-through system. Experiments were conducted as a function of total dissolved carbonate ([CO3-3]T) from 0.001 to 0.1 M; pH from 7.5 to 11.1; ratio of flow-through rate (q) to specific surface area (S), constant ionic strength (I) = 0.1 M, and temperatures (T) from 23 to 60 DGC utilizing both powder and monolithic specimens. The results show that UO2 dissolution varies as a function of the ratio q/S and temperature. At values of log10q/S > -7.0, UO2 dissolution becomes invariant with respect to q/S, which can be interpreted as evidence for dissolution at the forward rate of reaction. The data collected in these experiments show the rate of UO2 dissolution increased by an order of magnitude with a 30 DGC increase in temperature. The results also show the overall dissolution rate increases with an increase in pH and decreases as the dissolved uranium concentration approaches saturation with respect to secondary reaction products. Thus, as the value of the reaction quotient, Q, approaches equilibrium, K, (with respect to a potential secondary phase) the dissolution rate decreases. This decrease in dissolution rate (r) was also observed when comparing measured UO2 dissolution rates from static tests where r = 1.7 - 0.14 x 10-8 mol M-2 s-1 to the rate for flow-through reactors where r = 3.1 - 1.2 x 10-7 mol m-2 s-1. Thus, using traditional static test methods can result in an underestimation of the true forward rate of UO2(cr) dissolution. These results illustrate the importance of pH, solution saturation state, and the concentration of dissolved carbonate on the release of uranium from UO2 in the natural environment.</description><issn>0022-3115</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2005</creationdate><recordtype>article</recordtype><recordid>eNqNi8FqAjEURbNooVr9BCGrogvHlzgjtluZ4s6NriVk3pSMmWSa9wL9_FYtXRcuXLjnXCFmCgoFarPqii5k2xsuNEBVXKP0gxgBaL1cK1U9iTFRBz_wFaqR-Ki_Bkyux8DGywYZU--CYReDjK08wWFu00I2jij6fJsvLiA7S2-yblu0TFfxj5LhnO5_YsMoTWjksJ-Ix9Z4wulvP4uX9_q42y-HFD8zEp97Rxa9NwFjprPebstNWcL63-I3pTBRvg</recordid><startdate>20051015</startdate><enddate>20051015</enddate><creator>Pierce, E M</creator><creator>Icenhower, J P</creator><creator>Serne, R J</creator><creator>Catalano, J G</creator><scope>7SR</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>JG9</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20051015</creationdate><title>Experimental determination of U0O(cr) dissolution kinetics: Effects of solution saturation state and pH</title><author>Pierce, E M ; Icenhower, J P ; Serne, R J ; Catalano, J G</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-proquest_miscellaneous_288464403</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2005</creationdate><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Pierce, E M</creatorcontrib><creatorcontrib>Icenhower, J P</creatorcontrib><creatorcontrib>Serne, R J</creatorcontrib><creatorcontrib>Catalano, J G</creatorcontrib><collection>Engineered Materials 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>Civil Engineering Abstracts</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>Pierce, E M</au><au>Icenhower, J P</au><au>Serne, R J</au><au>Catalano, J G</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Experimental determination of U0O(cr) dissolution kinetics: Effects of solution saturation state and pH</atitle><jtitle>Journal of nuclear materials</jtitle><date>2005-10-15</date><risdate>2005</risdate><volume>345</volume><issue>2-3</issue><spage>206</spage><epage>218</epage><pages>206-218</pages><issn>0022-3115</issn><abstract>To evaluate the release of uranium from natural ore deposits, spent nuclear fuel repositories, and REDOX permeable reactive barriers (PRB), knowledge of the fundamental reaction kinetics associated with the dissolution of uranium dioxide is necessary. Dissolution of crystalline uranium (IV) dioxide under environmental conditions has been studied for four decades but a cardinal gap in the published literature is the effect of pH and solution saturation state on UO2(cr) dissolution. To resolve inconsistencies, UO2 dissolution experiments have been conducted under oxic conditions using the single-pass flow-through system. Experiments were conducted as a function of total dissolved carbonate ([CO3-3]T) from 0.001 to 0.1 M; pH from 7.5 to 11.1; ratio of flow-through rate (q) to specific surface area (S), constant ionic strength (I) = 0.1 M, and temperatures (T) from 23 to 60 DGC utilizing both powder and monolithic specimens. The results show that UO2 dissolution varies as a function of the ratio q/S and temperature. At values of log10q/S > -7.0, UO2 dissolution becomes invariant with respect to q/S, which can be interpreted as evidence for dissolution at the forward rate of reaction. The data collected in these experiments show the rate of UO2 dissolution increased by an order of magnitude with a 30 DGC increase in temperature. The results also show the overall dissolution rate increases with an increase in pH and decreases as the dissolved uranium concentration approaches saturation with respect to secondary reaction products. Thus, as the value of the reaction quotient, Q, approaches equilibrium, K, (with respect to a potential secondary phase) the dissolution rate decreases. This decrease in dissolution rate (r) was also observed when comparing measured UO2 dissolution rates from static tests where r = 1.7 - 0.14 x 10-8 mol M-2 s-1 to the rate for flow-through reactors where r = 3.1 - 1.2 x 10-7 mol m-2 s-1. Thus, using traditional static test methods can result in an underestimation of the true forward rate of UO2(cr) dissolution. These results illustrate the importance of pH, solution saturation state, and the concentration of dissolved carbonate on the release of uranium from UO2 in the natural environment.</abstract><doi>10.1016/j.jnucmat.2005.05.012</doi></addata></record> |
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title | Experimental determination of U0O(cr) dissolution kinetics: Effects of solution saturation state and pH |
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