Irradiation of thorium-bearing molten fluoride salt in graphite crucibles
•LiF-ThF4 molten salt fuel samples were irradiated in the HFR in graphite crucibles.•Purpose, design and assembly of the experiment, and in-pile data are discussed.•Contains ‘lessons learned’ relevant for future irradiation experiments. Four fluoride fuel salt samples (78LiF-22ThF4) in graphite cruc...
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| Veröffentlicht in: | Nuclear engineering and design 2021-04, Vol.375, p.111094, Article 111094 |
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| creator | Hania, P.R. Boomstra, D.A. Benes, O. Soucek, P. de Koning, A.J. Bobeldijk, I. de Groot, S. Konings, R.J.M. Capelli, E. Naji, M. Sciolla, C. Baas, P.J. Bhimanadam, V. Siccama, N.B. Lippens, G.I.A. |
| description | •LiF-ThF4 molten salt fuel samples were irradiated in the HFR in graphite crucibles.•Purpose, design and assembly of the experiment, and in-pile data are discussed.•Contains ‘lessons learned’ relevant for future irradiation experiments.
Four fluoride fuel salt samples (78LiF-22ThF4) in graphite crucibles were irradiated in the HFR Petten for a duration of 508 Full Power Days under the name SALIENT-01 (SALt Irradiation ExperimeNT). Goal of the experiment was to gain experience with the design of liquid salt experiments and the handling of the salts before and after irradiation. Specific research goals for SALIENT-01 are (i) to confirm claims of good fission product retention in the salt, (ii) to obtain size distributions for noble metal particles using Transmission Electron Microscopy and (iii) to assess possible interactions between fuel salt and fine-grained nuclear graphite, as well as possible uptake of fission products by the graphite. Here the design and irradiation history of the experiment are discussed together with plans for post-irradiation examinations. Limitations in representativeness of this experiment and capsule irradiations in general are discussed as well as follow-up actions to improve the quality of future irradiations. |
| doi_str_mv | 10.1016/j.nucengdes.2021.111094 |
| format | Article |
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Four fluoride fuel salt samples (78LiF-22ThF4) in graphite crucibles were irradiated in the HFR Petten for a duration of 508 Full Power Days under the name SALIENT-01 (SALt Irradiation ExperimeNT). Goal of the experiment was to gain experience with the design of liquid salt experiments and the handling of the salts before and after irradiation. Specific research goals for SALIENT-01 are (i) to confirm claims of good fission product retention in the salt, (ii) to obtain size distributions for noble metal particles using Transmission Electron Microscopy and (iii) to assess possible interactions between fuel salt and fine-grained nuclear graphite, as well as possible uptake of fission products by the graphite. Here the design and irradiation history of the experiment are discussed together with plans for post-irradiation examinations. Limitations in representativeness of this experiment and capsule irradiations in general are discussed as well as follow-up actions to improve the quality of future irradiations.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2021.111094</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Crucibles ; Design ; Experiments ; Fission product behaviour ; Fission products ; Fluorides ; Fuel ; Fuels ; Graphite ; Irradiation ; Metal particles ; Molten salt ; MTR irradiation ; Noble metals ; Nuclear fuels ; Post-irradiation ; Salts ; Thorium ; Transmission electron microscopy</subject><ispartof>Nuclear engineering and design, 2021-04, Vol.375, p.111094, Article 111094</ispartof><rights>2021 Elsevier B.V.</rights><rights>Copyright Elsevier BV Apr 15, 2021</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c343t-cef5fe6d54bd57b83030364aca56bcf27c14d5436f28f35edda1a29d88ae84b03</citedby><cites>FETCH-LOGICAL-c343t-cef5fe6d54bd57b83030364aca56bcf27c14d5436f28f35edda1a29d88ae84b03</cites><orcidid>0000-0002-8988-4310</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.nucengdes.2021.111094$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,780,784,3550,27924,27925,45995</link.rule.ids></links><search><creatorcontrib>Hania, P.R.</creatorcontrib><creatorcontrib>Boomstra, D.A.</creatorcontrib><creatorcontrib>Benes, O.</creatorcontrib><creatorcontrib>Soucek, P.</creatorcontrib><creatorcontrib>de Koning, A.J.</creatorcontrib><creatorcontrib>Bobeldijk, I.</creatorcontrib><creatorcontrib>de Groot, S.</creatorcontrib><creatorcontrib>Konings, R.J.M.</creatorcontrib><creatorcontrib>Capelli, E.</creatorcontrib><creatorcontrib>Naji, M.</creatorcontrib><creatorcontrib>Sciolla, C.</creatorcontrib><creatorcontrib>Baas, P.J.</creatorcontrib><creatorcontrib>Bhimanadam, V.</creatorcontrib><creatorcontrib>Siccama, N.B.</creatorcontrib><creatorcontrib>Lippens, G.I.A.</creatorcontrib><title>Irradiation of thorium-bearing molten fluoride salt in graphite crucibles</title><title>Nuclear engineering and design</title><description>•LiF-ThF4 molten salt fuel samples were irradiated in the HFR in graphite crucibles.•Purpose, design and assembly of the experiment, and in-pile data are discussed.•Contains ‘lessons learned’ relevant for future irradiation experiments.
Four fluoride fuel salt samples (78LiF-22ThF4) in graphite crucibles were irradiated in the HFR Petten for a duration of 508 Full Power Days under the name SALIENT-01 (SALt Irradiation ExperimeNT). Goal of the experiment was to gain experience with the design of liquid salt experiments and the handling of the salts before and after irradiation. Specific research goals for SALIENT-01 are (i) to confirm claims of good fission product retention in the salt, (ii) to obtain size distributions for noble metal particles using Transmission Electron Microscopy and (iii) to assess possible interactions between fuel salt and fine-grained nuclear graphite, as well as possible uptake of fission products by the graphite. Here the design and irradiation history of the experiment are discussed together with plans for post-irradiation examinations. Limitations in representativeness of this experiment and capsule irradiations in general are discussed as well as follow-up actions to improve the quality of future irradiations.</description><subject>Crucibles</subject><subject>Design</subject><subject>Experiments</subject><subject>Fission product behaviour</subject><subject>Fission products</subject><subject>Fluorides</subject><subject>Fuel</subject><subject>Fuels</subject><subject>Graphite</subject><subject>Irradiation</subject><subject>Metal particles</subject><subject>Molten salt</subject><subject>MTR irradiation</subject><subject>Noble metals</subject><subject>Nuclear fuels</subject><subject>Post-irradiation</subject><subject>Salts</subject><subject>Thorium</subject><subject>Transmission electron microscopy</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2021</creationdate><recordtype>article</recordtype><recordid>eNqFUE1LAzEQDaJgrf4GA5635mOzH8dS_CgIXhS8hWwyabNsszXJCv57U1a8OnMYmHnvDe8hdEvJihJa3fcrP2nwOwNxxQijK0opacsztKBNzYpatB_naEEIawtRtvwSXcXYk1O1bIG22xCUcSq50ePR4rQfg5sORQcqOL_Dh3FI4LEdprw3gKMaEnYe74I67l0CrMOkXTdAvEYXVg0Rbn7nEr0_PrxtnouX16ftZv1SaF7yVGiwwkJlRNkZUXcNJ7mrUmklqk5bVmta5iOvLGssF2CMooq1pmkUNGVH-BLdzbrHMH5OEJPsxyn4_FIywbJ5Xlcio-oZpcMYYwArj8EdVPiWlMhTbrKXf7nJU25yzi0z1zMTsokvB0FG7cBrMC6ATtKM7l-NH4Abe8E</recordid><startdate>20210415</startdate><enddate>20210415</enddate><creator>Hania, P.R.</creator><creator>Boomstra, D.A.</creator><creator>Benes, O.</creator><creator>Soucek, P.</creator><creator>de Koning, A.J.</creator><creator>Bobeldijk, I.</creator><creator>de Groot, S.</creator><creator>Konings, R.J.M.</creator><creator>Capelli, E.</creator><creator>Naji, M.</creator><creator>Sciolla, C.</creator><creator>Baas, P.J.</creator><creator>Bhimanadam, V.</creator><creator>Siccama, N.B.</creator><creator>Lippens, G.I.A.</creator><general>Elsevier B.V</general><general>Elsevier BV</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7ST</scope><scope>7TB</scope><scope>8FD</scope><scope>C1K</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope><scope>SOI</scope><orcidid>https://orcid.org/0000-0002-8988-4310</orcidid></search><sort><creationdate>20210415</creationdate><title>Irradiation of thorium-bearing molten fluoride salt in graphite crucibles</title><author>Hania, P.R. ; Boomstra, D.A. ; Benes, O. ; Soucek, P. ; de Koning, A.J. ; Bobeldijk, I. ; de Groot, S. ; Konings, R.J.M. ; Capelli, E. ; Naji, M. ; Sciolla, C. ; Baas, P.J. ; Bhimanadam, V. ; Siccama, N.B. ; Lippens, G.I.A.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c343t-cef5fe6d54bd57b83030364aca56bcf27c14d5436f28f35edda1a29d88ae84b03</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2021</creationdate><topic>Crucibles</topic><topic>Design</topic><topic>Experiments</topic><topic>Fission product behaviour</topic><topic>Fission products</topic><topic>Fluorides</topic><topic>Fuel</topic><topic>Fuels</topic><topic>Graphite</topic><topic>Irradiation</topic><topic>Metal particles</topic><topic>Molten salt</topic><topic>MTR irradiation</topic><topic>Noble metals</topic><topic>Nuclear fuels</topic><topic>Post-irradiation</topic><topic>Salts</topic><topic>Thorium</topic><topic>Transmission electron microscopy</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Hania, P.R.</creatorcontrib><creatorcontrib>Boomstra, D.A.</creatorcontrib><creatorcontrib>Benes, O.</creatorcontrib><creatorcontrib>Soucek, P.</creatorcontrib><creatorcontrib>de Koning, A.J.</creatorcontrib><creatorcontrib>Bobeldijk, I.</creatorcontrib><creatorcontrib>de Groot, S.</creatorcontrib><creatorcontrib>Konings, R.J.M.</creatorcontrib><creatorcontrib>Capelli, E.</creatorcontrib><creatorcontrib>Naji, M.</creatorcontrib><creatorcontrib>Sciolla, C.</creatorcontrib><creatorcontrib>Baas, P.J.</creatorcontrib><creatorcontrib>Bhimanadam, V.</creatorcontrib><creatorcontrib>Siccama, N.B.</creatorcontrib><creatorcontrib>Lippens, G.I.A.</creatorcontrib><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Environment Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Environment Abstracts</collection><jtitle>Nuclear engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Hania, P.R.</au><au>Boomstra, D.A.</au><au>Benes, O.</au><au>Soucek, P.</au><au>de Koning, A.J.</au><au>Bobeldijk, I.</au><au>de Groot, S.</au><au>Konings, R.J.M.</au><au>Capelli, E.</au><au>Naji, M.</au><au>Sciolla, C.</au><au>Baas, P.J.</au><au>Bhimanadam, V.</au><au>Siccama, N.B.</au><au>Lippens, G.I.A.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Irradiation of thorium-bearing molten fluoride salt in graphite crucibles</atitle><jtitle>Nuclear engineering and design</jtitle><date>2021-04-15</date><risdate>2021</risdate><volume>375</volume><spage>111094</spage><pages>111094-</pages><artnum>111094</artnum><issn>0029-5493</issn><eissn>1872-759X</eissn><abstract>•LiF-ThF4 molten salt fuel samples were irradiated in the HFR in graphite crucibles.•Purpose, design and assembly of the experiment, and in-pile data are discussed.•Contains ‘lessons learned’ relevant for future irradiation experiments.
Four fluoride fuel salt samples (78LiF-22ThF4) in graphite crucibles were irradiated in the HFR Petten for a duration of 508 Full Power Days under the name SALIENT-01 (SALt Irradiation ExperimeNT). Goal of the experiment was to gain experience with the design of liquid salt experiments and the handling of the salts before and after irradiation. Specific research goals for SALIENT-01 are (i) to confirm claims of good fission product retention in the salt, (ii) to obtain size distributions for noble metal particles using Transmission Electron Microscopy and (iii) to assess possible interactions between fuel salt and fine-grained nuclear graphite, as well as possible uptake of fission products by the graphite. Here the design and irradiation history of the experiment are discussed together with plans for post-irradiation examinations. Limitations in representativeness of this experiment and capsule irradiations in general are discussed as well as follow-up actions to improve the quality of future irradiations.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2021.111094</doi><orcidid>https://orcid.org/0000-0002-8988-4310</orcidid></addata></record> |
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| subjects | Crucibles Design Experiments Fission product behaviour Fission products Fluorides Fuel Fuels Graphite Irradiation Metal particles Molten salt MTR irradiation Noble metals Nuclear fuels Post-irradiation Salts Thorium Transmission electron microscopy |
| title | Irradiation of thorium-bearing molten fluoride salt in graphite crucibles |
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