Swelling of Uranium Dioxide–Silumin Dispersion Fuel Composition in Experimental Fuel Elements of the SM Reactor
A variant of experimental dispersion fuel elements with a displacer and uranium dioxide-silumin fuel composition, which were proposed for modernizing the core of the SM reactor, was investigated. The fuel elements were irradiated in a wide spectrum of neutron- and thermophysical parameters of the re...
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| Veröffentlicht in: | Atomic energy (New York, N.Y.) N.Y.), 2018-05, Vol.124 (1), p.28-35 |
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| creator | Gil’mutdinov, I. F. Shishin, V. Yu Kryukov, F. N. Kuz’min, S. V. Silant’ev, P. P. Minduksheva, I. A. Starkov, V. A. Pimenov, V. V. |
| description | A variant of experimental dispersion fuel elements with a displacer and uranium dioxide-silumin fuel composition, which were proposed for modernizing the core of the SM reactor, was investigated. The fuel elements were irradiated in a wide spectrum of neutron- and thermophysical parameters of the reactor’s reflector channel. The fuel elements showed satisfactory radiation resistance at thermal flux density 5.8–8 MW/m
2
and burnup to 45%. The swelling of the fuel composition was analyzed. It is shown that of three possible components of the swelling the one due to gaseous fission products makes the main contribution, approximately 3/4 of the total amount. The interaction of the fuel components results in compaction of the kernel and promotes some compensation of the swelling, increasing as the interaction increases. These investigations show that the depth of burnup at the achieved thermal flux density for fuel elements with a displacer is not the limit. |
| doi_str_mv | 10.1007/s10512-018-0370-0 |
| format | Article |
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2
and burnup to 45%. The swelling of the fuel composition was analyzed. It is shown that of three possible components of the swelling the one due to gaseous fission products makes the main contribution, approximately 3/4 of the total amount. The interaction of the fuel components results in compaction of the kernel and promotes some compensation of the swelling, increasing as the interaction increases. These investigations show that the depth of burnup at the achieved thermal flux density for fuel elements with a displacer is not the limit.</description><identifier>ISSN: 1063-4258</identifier><identifier>EISSN: 1573-8205</identifier><identifier>DOI: 10.1007/s10512-018-0370-0</identifier><language>eng</language><publisher>New York: Springer US</publisher><subject>BURNUP ; Composition ; Dispersion ; DISPERSION NUCLEAR FUELS ; Energy industry ; FISSION PRODUCTS ; FLUX DENSITY ; FUEL ELEMENTS ; GENERAL STUDIES OF NUCLEAR REACTORS ; Hadrons ; Heat transfer ; Heat transmission ; Heavy Ions ; IRRADIATION ; Modernization ; Neutron flux ; NEUTRONS ; Nuclear Chemistry ; Nuclear Energy ; Nuclear fuel elements ; Nuclear fuels ; Nuclear Physics ; Nuclear power plants ; Physics ; Physics and Astronomy ; Radiation (Physics) ; Radiation tolerance ; Reactors ; Silicon alloys ; SWELLING ; Thermal resistance ; Uranium ; Uranium compounds ; URANIUM DIOXIDE ; Uranium ores</subject><ispartof>Atomic energy (New York, N.Y.), 2018-05, Vol.124 (1), p.28-35</ispartof><rights>Springer Science+Business Media, LLC, part of Springer Nature 2018</rights><rights>COPYRIGHT 2018 Springer</rights><rights>Atomic Energy is a copyright of Springer, (2018). All Rights Reserved.</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c417t-80037646d8a842d599d689dfe1da062f1f5efa3178158a8e48b9910475a18db23</citedby><cites>FETCH-LOGICAL-c417t-80037646d8a842d599d689dfe1da062f1f5efa3178158a8e48b9910475a18db23</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://link.springer.com/content/pdf/10.1007/s10512-018-0370-0$$EPDF$$P50$$Gspringer$$H</linktopdf><linktohtml>$$Uhttps://link.springer.com/10.1007/s10512-018-0370-0$$EHTML$$P50$$Gspringer$$H</linktohtml><link.rule.ids>230,315,781,785,886,27929,27930,41493,42562,51324</link.rule.ids><backlink>$$Uhttps://www.osti.gov/biblio/22810032$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Gil’mutdinov, I. F.</creatorcontrib><creatorcontrib>Shishin, V. Yu</creatorcontrib><creatorcontrib>Kryukov, F. N.</creatorcontrib><creatorcontrib>Kuz’min, S. V.</creatorcontrib><creatorcontrib>Silant’ev, P. P.</creatorcontrib><creatorcontrib>Minduksheva, I. A.</creatorcontrib><creatorcontrib>Starkov, V. A.</creatorcontrib><creatorcontrib>Pimenov, V. V.</creatorcontrib><title>Swelling of Uranium Dioxide–Silumin Dispersion Fuel Composition in Experimental Fuel Elements of the SM Reactor</title><title>Atomic energy (New York, N.Y.)</title><addtitle>At Energy</addtitle><description>A variant of experimental dispersion fuel elements with a displacer and uranium dioxide-silumin fuel composition, which were proposed for modernizing the core of the SM reactor, was investigated. The fuel elements were irradiated in a wide spectrum of neutron- and thermophysical parameters of the reactor’s reflector channel. The fuel elements showed satisfactory radiation resistance at thermal flux density 5.8–8 MW/m
2
and burnup to 45%. The swelling of the fuel composition was analyzed. It is shown that of three possible components of the swelling the one due to gaseous fission products makes the main contribution, approximately 3/4 of the total amount. The interaction of the fuel components results in compaction of the kernel and promotes some compensation of the swelling, increasing as the interaction increases. These investigations show that the depth of burnup at the achieved thermal flux density for fuel elements with a displacer is not the limit.</description><subject>BURNUP</subject><subject>Composition</subject><subject>Dispersion</subject><subject>DISPERSION NUCLEAR FUELS</subject><subject>Energy industry</subject><subject>FISSION PRODUCTS</subject><subject>FLUX DENSITY</subject><subject>FUEL ELEMENTS</subject><subject>GENERAL STUDIES OF NUCLEAR REACTORS</subject><subject>Hadrons</subject><subject>Heat transfer</subject><subject>Heat transmission</subject><subject>Heavy Ions</subject><subject>IRRADIATION</subject><subject>Modernization</subject><subject>Neutron flux</subject><subject>NEUTRONS</subject><subject>Nuclear Chemistry</subject><subject>Nuclear Energy</subject><subject>Nuclear fuel elements</subject><subject>Nuclear fuels</subject><subject>Nuclear Physics</subject><subject>Nuclear power plants</subject><subject>Physics</subject><subject>Physics and Astronomy</subject><subject>Radiation (Physics)</subject><subject>Radiation tolerance</subject><subject>Reactors</subject><subject>Silicon alloys</subject><subject>SWELLING</subject><subject>Thermal resistance</subject><subject>Uranium</subject><subject>Uranium compounds</subject><subject>URANIUM DIOXIDE</subject><subject>Uranium ores</subject><issn>1063-4258</issn><issn>1573-8205</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2018</creationdate><recordtype>article</recordtype><sourceid>ABUWG</sourceid><sourceid>AFKRA</sourceid><sourceid>AZQEC</sourceid><sourceid>BENPR</sourceid><sourceid>CCPQU</sourceid><sourceid>DWQXO</sourceid><sourceid>GNUQQ</sourceid><recordid>eNp1kc9q3DAQxkVpoOmmD9CboacenIxkyZaPYbtJAymFbHMWij3aKNjSRpLJ9tZ3yBv2SSLjQptDEejPzO8bRvMR8pHCKQVoziIFQVkJVJZQNVDCG3JMRVOVkoF4m-9QVyVnQr4j72N8AIC2buUxedw-4TBYtyu8KW6DdnYaiy_WH2yPv389b-0wjdblSNxjiNa74mLCoVj7ce-jTXMgpzeHnLUjuqSHBdgMOD_jXDbdY7H9Vtyg7pIPJ-TI6CHihz_nitxebH6sv5bX3y-v1ufXZcdpk0oJ-R81r3upJWe9aNu-lm1vkPYaamaoEWh0RRtJRUaQy7u2pcAboans71i1Ip-Wuj4mq2JnE3b3nXcOu6QYk3ls1T_UPvjHCWNSD34KLjemGHAOlAnaZOp0oXZ6QGWd8SnoLq8eR5trorE5fi44r2toYRZ8fiXITMJD2ukpRnW1vXnN0oXtgo8xoFH7PEsdfioKajZXLeaqbK6azc3birBFEzPrdhj-tv1_0QvTY6Wr</recordid><startdate>20180501</startdate><enddate>20180501</enddate><creator>Gil’mutdinov, I. 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F.</au><au>Shishin, V. Yu</au><au>Kryukov, F. N.</au><au>Kuz’min, S. V.</au><au>Silant’ev, P. P.</au><au>Minduksheva, I. A.</au><au>Starkov, V. A.</au><au>Pimenov, V. V.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Swelling of Uranium Dioxide–Silumin Dispersion Fuel Composition in Experimental Fuel Elements of the SM Reactor</atitle><jtitle>Atomic energy (New York, N.Y.)</jtitle><stitle>At Energy</stitle><date>2018-05-01</date><risdate>2018</risdate><volume>124</volume><issue>1</issue><spage>28</spage><epage>35</epage><pages>28-35</pages><issn>1063-4258</issn><eissn>1573-8205</eissn><abstract>A variant of experimental dispersion fuel elements with a displacer and uranium dioxide-silumin fuel composition, which were proposed for modernizing the core of the SM reactor, was investigated. The fuel elements were irradiated in a wide spectrum of neutron- and thermophysical parameters of the reactor’s reflector channel. The fuel elements showed satisfactory radiation resistance at thermal flux density 5.8–8 MW/m
2
and burnup to 45%. The swelling of the fuel composition was analyzed. It is shown that of three possible components of the swelling the one due to gaseous fission products makes the main contribution, approximately 3/4 of the total amount. The interaction of the fuel components results in compaction of the kernel and promotes some compensation of the swelling, increasing as the interaction increases. These investigations show that the depth of burnup at the achieved thermal flux density for fuel elements with a displacer is not the limit.</abstract><cop>New York</cop><pub>Springer US</pub><doi>10.1007/s10512-018-0370-0</doi><tpages>8</tpages></addata></record> |
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| ispartof | Atomic energy (New York, N.Y.), 2018-05, Vol.124 (1), p.28-35 |
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| recordid | cdi_osti_scitechconnect_22810032 |
| source | SpringerNature Journals |
| subjects | BURNUP Composition Dispersion DISPERSION NUCLEAR FUELS Energy industry FISSION PRODUCTS FLUX DENSITY FUEL ELEMENTS GENERAL STUDIES OF NUCLEAR REACTORS Hadrons Heat transfer Heat transmission Heavy Ions IRRADIATION Modernization Neutron flux NEUTRONS Nuclear Chemistry Nuclear Energy Nuclear fuel elements Nuclear fuels Nuclear Physics Nuclear power plants Physics Physics and Astronomy Radiation (Physics) Radiation tolerance Reactors Silicon alloys SWELLING Thermal resistance Uranium Uranium compounds URANIUM DIOXIDE Uranium ores |
| title | Swelling of Uranium Dioxide–Silumin Dispersion Fuel Composition in Experimental Fuel Elements of the SM Reactor |
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