Accident testing of high-temperature reactor fuel elements from the HFR-EU1bis irradiation
► Accident testing of two HFR-EU1bis high-temperature reactor fuel elements. ► Simulation of depressurization and loss of forced circulation (D-LOFC) up to 1800 °C. ► Low fractional release of Kr-85 indicates no particle failure during heating test. ► Fractional release of Cs and Ag higher than in p...
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| Veröffentlicht in: | Nuclear engineering and design 2011-08, Vol.241 (8), p.2813-2821 |
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| container_title | Nuclear engineering and design |
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| creator | Freis, D. Bottomley, P.D.W. Kellerbauer, A.I. Rondinella, V.V. Van Uffelen, P. |
| description | ► Accident testing of two HFR-EU1bis high-temperature reactor fuel elements. ► Simulation of depressurization and loss of forced circulation (D-LOFC) up to 1800
°C. ► Low fractional release of Kr-85 indicates no particle failure during heating test. ► Fractional release of Cs and Ag higher than in previous studies. ► Finite-difference method calculation reproduces experimental results.
Four spherical high-temperature reactor fuel elements irradiated at the High Flux Reactor in Petten within the HFR-EU1bis irradiation campaign were transported to JRC-ITU for post-irradiation examination and accident testing. This article reports the accident tests performed on the first two fuel elements HFR-EU1bis/1 and HFR-EU1bis/3 with the Küfa device. The fuel elements were heated up to the irradiation temperature (1250
°C) and then to accident temperatures (1600
°C and 1700
°C, respectively) for durations of several hundred hours to simulate depressurization and loss-of-forced-circulation accidents (D-LOFC). The overall low fractional release of
85Kr and the absence of steps in the release curves suggest that no coated particles failed during the accident simulations. On the other hand, the fractional release of
134Cs and
137Cs was much higher than in previous experiments, indicating increased diffusion through the coating layers at the higher irradiation temperature, as confirmed with a finite-difference diffusion calculation. Finally, the calculation suggests that the high fractional silver and cesium releases at 1250
°C are due to a matrix contamination prior to the Küfa accident testing. |
| doi_str_mv | 10.1016/j.nucengdes.2011.05.026 |
| format | Article |
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°C. ► Low fractional release of Kr-85 indicates no particle failure during heating test. ► Fractional release of Cs and Ag higher than in previous studies. ► Finite-difference method calculation reproduces experimental results.
Four spherical high-temperature reactor fuel elements irradiated at the High Flux Reactor in Petten within the HFR-EU1bis irradiation campaign were transported to JRC-ITU for post-irradiation examination and accident testing. This article reports the accident tests performed on the first two fuel elements HFR-EU1bis/1 and HFR-EU1bis/3 with the Küfa device. The fuel elements were heated up to the irradiation temperature (1250
°C) and then to accident temperatures (1600
°C and 1700
°C, respectively) for durations of several hundred hours to simulate depressurization and loss-of-forced-circulation accidents (D-LOFC). The overall low fractional release of
85Kr and the absence of steps in the release curves suggest that no coated particles failed during the accident simulations. On the other hand, the fractional release of
134Cs and
137Cs was much higher than in previous experiments, indicating increased diffusion through the coating layers at the higher irradiation temperature, as confirmed with a finite-difference diffusion calculation. Finally, the calculation suggests that the high fractional silver and cesium releases at 1250
°C are due to a matrix contamination prior to the Küfa accident testing.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2011.05.026</identifier><identifier>CODEN: NEDEAU</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Accidents ; Applied sciences ; Controled nuclear fusion plants ; Diffusion ; Diffusion layers ; 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 ; Irradiation ; Mathematical analysis ; Nuclear fuel elements ; Nuclear fuels ; Nuclear reactor components ; Nuclear reactors</subject><ispartof>Nuclear engineering and design, 2011-08, Vol.241 (8), p.2813-2821</ispartof><rights>2011 Elsevier B.V.</rights><rights>2015 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c410t-580ba3aff5eb88c99690ba67bae2a6d6bd69dec8cbb28061d3fc964c3c07c5273</citedby><cites>FETCH-LOGICAL-c410t-580ba3aff5eb88c99690ba67bae2a6d6bd69dec8cbb28061d3fc964c3c07c5273</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.nucengdes.2011.05.026$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,777,781,3537,27905,27906,45976</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=24453767$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Freis, D.</creatorcontrib><creatorcontrib>Bottomley, P.D.W.</creatorcontrib><creatorcontrib>Kellerbauer, A.I.</creatorcontrib><creatorcontrib>Rondinella, V.V.</creatorcontrib><creatorcontrib>Van Uffelen, P.</creatorcontrib><title>Accident testing of high-temperature reactor fuel elements from the HFR-EU1bis irradiation</title><title>Nuclear engineering and design</title><description>► Accident testing of two HFR-EU1bis high-temperature reactor fuel elements. ► Simulation of depressurization and loss of forced circulation (D-LOFC) up to 1800
°C. ► Low fractional release of Kr-85 indicates no particle failure during heating test. ► Fractional release of Cs and Ag higher than in previous studies. ► Finite-difference method calculation reproduces experimental results.
Four spherical high-temperature reactor fuel elements irradiated at the High Flux Reactor in Petten within the HFR-EU1bis irradiation campaign were transported to JRC-ITU for post-irradiation examination and accident testing. This article reports the accident tests performed on the first two fuel elements HFR-EU1bis/1 and HFR-EU1bis/3 with the Küfa device. The fuel elements were heated up to the irradiation temperature (1250
°C) and then to accident temperatures (1600
°C and 1700
°C, respectively) for durations of several hundred hours to simulate depressurization and loss-of-forced-circulation accidents (D-LOFC). The overall low fractional release of
85Kr and the absence of steps in the release curves suggest that no coated particles failed during the accident simulations. On the other hand, the fractional release of
134Cs and
137Cs was much higher than in previous experiments, indicating increased diffusion through the coating layers at the higher irradiation temperature, as confirmed with a finite-difference diffusion calculation. Finally, the calculation suggests that the high fractional silver and cesium releases at 1250
°C are due to a matrix contamination prior to the Küfa accident testing.</description><subject>Accidents</subject><subject>Applied sciences</subject><subject>Controled nuclear fusion plants</subject><subject>Diffusion</subject><subject>Diffusion layers</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>Irradiation</subject><subject>Mathematical analysis</subject><subject>Nuclear fuel elements</subject><subject>Nuclear fuels</subject><subject>Nuclear reactor components</subject><subject>Nuclear reactors</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2011</creationdate><recordtype>article</recordtype><recordid>eNqFkEtr3DAUhUVpIdNpfkO0Ke3GriTbkrUcQtIUAoHSQMlGyFdXMxr8mEpyIP--NhOybO_mwOWc-_gIueKs5IzLb8dynAHHvcNUCsZ5yZqSCfmObHirRKEa_fs92TAmdNHUurogH1M6srW02JCnHUBwOGaaMeUw7unk6SHsD0XG4YTR5jkijWghT5H6GXuKPQ5LIFEfp4HmA9K725_FzSPvQqIhRuuCzWEaP5EP3vYJL191Sx5vb35d3xX3D99_XO_uC6g5y0XTss5W1vsGu7YFraVeGlJ1FoWVTnZOaofQQteJlknuKg9a1lABU9AIVW3Jl_PcU5z-zMsXZggJsO_tiNOcTKsrIRVbZEu-_tPJlVK8ZpytVnW2QpxSiujNKYbBxhfDmVm5m6N5425W7oY1ZuG-JD-_LrEJbO-jHSGkt7io66ZScj17d_bhwuY5YDQJAo6ALkSEbNwU_rvrL5qFniE</recordid><startdate>20110801</startdate><enddate>20110801</enddate><creator>Freis, D.</creator><creator>Bottomley, P.D.W.</creator><creator>Kellerbauer, A.I.</creator><creator>Rondinella, V.V.</creator><creator>Van Uffelen, P.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7SU</scope><scope>7TB</scope><scope>8FD</scope><scope>C1K</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope><scope>7T2</scope><scope>7U2</scope></search><sort><creationdate>20110801</creationdate><title>Accident testing of high-temperature reactor fuel elements from the HFR-EU1bis irradiation</title><author>Freis, D. ; Bottomley, P.D.W. ; Kellerbauer, A.I. ; Rondinella, V.V. ; Van Uffelen, P.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c410t-580ba3aff5eb88c99690ba67bae2a6d6bd69dec8cbb28061d3fc964c3c07c5273</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2011</creationdate><topic>Accidents</topic><topic>Applied sciences</topic><topic>Controled nuclear fusion plants</topic><topic>Diffusion</topic><topic>Diffusion layers</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>Irradiation</topic><topic>Mathematical analysis</topic><topic>Nuclear fuel elements</topic><topic>Nuclear fuels</topic><topic>Nuclear reactor components</topic><topic>Nuclear reactors</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Freis, D.</creatorcontrib><creatorcontrib>Bottomley, P.D.W.</creatorcontrib><creatorcontrib>Kellerbauer, A.I.</creatorcontrib><creatorcontrib>Rondinella, V.V.</creatorcontrib><creatorcontrib>Van Uffelen, P.</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Environmental Engineering 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>Health and Safety Science Abstracts (Full archive)</collection><collection>Safety Science and Risk</collection><jtitle>Nuclear engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Freis, D.</au><au>Bottomley, P.D.W.</au><au>Kellerbauer, A.I.</au><au>Rondinella, V.V.</au><au>Van Uffelen, P.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Accident testing of high-temperature reactor fuel elements from the HFR-EU1bis irradiation</atitle><jtitle>Nuclear engineering and design</jtitle><date>2011-08-01</date><risdate>2011</risdate><volume>241</volume><issue>8</issue><spage>2813</spage><epage>2821</epage><pages>2813-2821</pages><issn>0029-5493</issn><eissn>1872-759X</eissn><coden>NEDEAU</coden><abstract>► Accident testing of two HFR-EU1bis high-temperature reactor fuel elements. ► Simulation of depressurization and loss of forced circulation (D-LOFC) up to 1800
°C. ► Low fractional release of Kr-85 indicates no particle failure during heating test. ► Fractional release of Cs and Ag higher than in previous studies. ► Finite-difference method calculation reproduces experimental results.
Four spherical high-temperature reactor fuel elements irradiated at the High Flux Reactor in Petten within the HFR-EU1bis irradiation campaign were transported to JRC-ITU for post-irradiation examination and accident testing. This article reports the accident tests performed on the first two fuel elements HFR-EU1bis/1 and HFR-EU1bis/3 with the Küfa device. The fuel elements were heated up to the irradiation temperature (1250
°C) and then to accident temperatures (1600
°C and 1700
°C, respectively) for durations of several hundred hours to simulate depressurization and loss-of-forced-circulation accidents (D-LOFC). The overall low fractional release of
85Kr and the absence of steps in the release curves suggest that no coated particles failed during the accident simulations. On the other hand, the fractional release of
134Cs and
137Cs was much higher than in previous experiments, indicating increased diffusion through the coating layers at the higher irradiation temperature, as confirmed with a finite-difference diffusion calculation. Finally, the calculation suggests that the high fractional silver and cesium releases at 1250
°C are due to a matrix contamination prior to the Küfa accident testing.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2011.05.026</doi><tpages>9</tpages></addata></record> |
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| source | Elsevier ScienceDirect Journals |
| subjects | Accidents Applied sciences Controled nuclear fusion plants Diffusion Diffusion layers 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 Irradiation Mathematical analysis Nuclear fuel elements Nuclear fuels Nuclear reactor components Nuclear reactors |
| title | Accident testing of high-temperature reactor fuel elements from the HFR-EU1bis irradiation |
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