Europium diffusion in IG-110 nuclear graphite
Europium diffusion in graphite has been recognized to be of interest in high-temperature gas reactor safety analysis, particularly as an indicator of strontium diffusion. However, no measurements of europium diffusion coefficients have been reported in the literature. In this work, the effective dif...
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Veröffentlicht in: | Journal of nuclear materials 2022-04, Vol.561 (C), p.153544, Article 153544 |
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creator | Weilert, T.M. Walton, K.L. Loyalka, S.K. Brockman, J.D. |
description | Europium diffusion in graphite has been recognized to be of interest in high-temperature gas reactor safety analysis, particularly as an indicator of strontium diffusion. However, no measurements of europium diffusion coefficients have been reported in the literature. In this work, the effective diffusion coefficient of europium was measured using a time-release method. Natural europium was loaded into pre-milled unirradiated IG-110 graphite spheres using a pressurized acid digestion vessel. The time-release experiments were performed in the temperature range 1823 K – 1973 K using a SiC diffusion cell connected to an inductively-coupled plasma mass spectrometer (ICP-MS) via a He gas line. The results of this work are:
DEu,IG−110=(1.5×10−3m2/s)exp(−2.87×105J/molRT)This effective diffusion coefficient can be used to aid in predictive modelling of europium transport in HTGRs. |
doi_str_mv | 10.1016/j.jnucmat.2022.153544 |
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DEu,IG−110=(1.5×10−3m2/s)exp(−2.87×105J/molRT)This effective diffusion coefficient can be used to aid in predictive modelling of europium transport in HTGRs.</description><subject>Acid digestion</subject><subject>Diffusion</subject><subject>Diffusion cells</subject><subject>Diffusion coefficient</subject><subject>Europium</subject><subject>Graphite</subject><subject>High temperature gases</subject><subject>HTGR</subject><subject>IG-110</subject><subject>Immunoglobulins</subject><subject>Inductively coupled plasma mass spectrometry</subject><subject>MATERIALS SCIENCE</subject><subject>Nuclear safety</subject><subject>Nuclear Science & Technology</subject><subject>Prediction models</subject><subject>Reactor safety</subject><subject>Silicon carbide</subject><subject>Strontium</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2022</creationdate><recordtype>article</recordtype><recordid>eNqFkMFOwzAQRC0EEqXwCUgRnBO83tiJTwhVUCpV4gJnK3Fs6qiNg50g8fekpHdOe9iZ2dlHyC3QDCiIhzZru1EfqiFjlLEMOPI8PyMLKAtM85LRc7Kg0yZFAH5JrmJsKaVcUr4g6fMYfO_GQ9I4a8fofJe4LtmsUwCaTLF7U4XkM1T9zg3mmlzYah_NzWkuycfL8_vqNd2-rTerp22qc4AhZTVqtFzISjdItag1k2BlaWpRI0ULFqgGbmiN0gpZ1I1tUCCWhbBQ5wyX5G7O9XFwKurptN5p33VGDwpkUWDBJ9H9LOqD_xpNHFTrx9BNvRQTKAtk5V8Un1U6-BiDsaoP7lCFHwVUHfGpVp3wqSM-NeObfI-zz0x_fjsTjjVMp03jwrFF490_Cb_NkHiS</recordid><startdate>20220401</startdate><enddate>20220401</enddate><creator>Weilert, T.M.</creator><creator>Walton, K.L.</creator><creator>Loyalka, S.K.</creator><creator>Brockman, J.D.</creator><general>Elsevier B.V</general><general>Elsevier BV</general><general>Elsevier</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7QQ</scope><scope>7SR</scope><scope>7ST</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>C1K</scope><scope>FR3</scope><scope>JG9</scope><scope>L7M</scope><scope>SOI</scope><scope>OIOZB</scope><scope>OTOTI</scope></search><sort><creationdate>20220401</creationdate><title>Europium diffusion in IG-110 nuclear graphite</title><author>Weilert, T.M. ; Walton, K.L. ; Loyalka, S.K. ; Brockman, J.D.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c411t-2b3c3f569acd30c6bc291f98eb6b303f1f10c15e0b39f697bdfd3633876f1b423</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2022</creationdate><topic>Acid digestion</topic><topic>Diffusion</topic><topic>Diffusion cells</topic><topic>Diffusion coefficient</topic><topic>Europium</topic><topic>Graphite</topic><topic>High temperature gases</topic><topic>HTGR</topic><topic>IG-110</topic><topic>Immunoglobulins</topic><topic>Inductively coupled plasma mass spectrometry</topic><topic>MATERIALS SCIENCE</topic><topic>Nuclear safety</topic><topic>Nuclear Science & Technology</topic><topic>Prediction models</topic><topic>Reactor safety</topic><topic>Silicon carbide</topic><topic>Strontium</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Weilert, T.M.</creatorcontrib><creatorcontrib>Walton, K.L.</creatorcontrib><creatorcontrib>Loyalka, S.K.</creatorcontrib><creatorcontrib>Brockman, J.D.</creatorcontrib><creatorcontrib>Univ. of Missouri, Columbia, MO (United States)</creatorcontrib><collection>CrossRef</collection><collection>Ceramic Abstracts</collection><collection>Engineered Materials Abstracts</collection><collection>Environment Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Engineering Research Database</collection><collection>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Environment Abstracts</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>Weilert, T.M.</au><au>Walton, K.L.</au><au>Loyalka, S.K.</au><au>Brockman, J.D.</au><aucorp>Univ. of Missouri, Columbia, MO (United States)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Europium diffusion in IG-110 nuclear graphite</atitle><jtitle>Journal of nuclear materials</jtitle><date>2022-04-01</date><risdate>2022</risdate><volume>561</volume><issue>C</issue><spage>153544</spage><pages>153544-</pages><artnum>153544</artnum><issn>0022-3115</issn><eissn>1873-4820</eissn><abstract>Europium diffusion in graphite has been recognized to be of interest in high-temperature gas reactor safety analysis, particularly as an indicator of strontium diffusion. However, no measurements of europium diffusion coefficients have been reported in the literature. In this work, the effective diffusion coefficient of europium was measured using a time-release method. Natural europium was loaded into pre-milled unirradiated IG-110 graphite spheres using a pressurized acid digestion vessel. The time-release experiments were performed in the temperature range 1823 K – 1973 K using a SiC diffusion cell connected to an inductively-coupled plasma mass spectrometer (ICP-MS) via a He gas line. The results of this work are:
DEu,IG−110=(1.5×10−3m2/s)exp(−2.87×105J/molRT)This effective diffusion coefficient can be used to aid in predictive modelling of europium transport in HTGRs.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2022.153544</doi><oa>free_for_read</oa></addata></record> |
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subjects | Acid digestion Diffusion Diffusion cells Diffusion coefficient Europium Graphite High temperature gases HTGR IG-110 Immunoglobulins Inductively coupled plasma mass spectrometry MATERIALS SCIENCE Nuclear safety Nuclear Science & Technology Prediction models Reactor safety Silicon carbide Strontium |
title | Europium diffusion in IG-110 nuclear graphite |
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