Evaluation of the Possibility of Using the Full Load of MOX Fuel in the VVER-600 Reactor
In this paper, we analyze the possibility of using 100% MOX fuel (mixed oxide uranium-plutonium fuel) in a VVER-600 reactor with nominal power of 1600 MW(t). The VVER-600 core consists of 163 fuel assemblies (FAs) similar in design to VVER-TOI fuel assemblies. MOX fuel contains tailings of uranium (...
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| Veröffentlicht in: | Physics of atomic nuclei 2023-12, Vol.86 (8), p.1856-1862 |
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| creator | Trapeznikov, I. N. Ponomarenko, G. L. Vasilchenko, I. N. |
| description | In this paper, we analyze the possibility of using 100% MOX fuel (mixed oxide uranium-plutonium fuel) in a VVER-600 reactor with nominal power of 1600 MW(t). The VVER-600 core consists of 163 fuel assemblies (FAs) similar in design to VVER-TOI fuel assemblies. MOX fuel contains tailings of uranium (99.8%
238
U and 0.2%
235
U) and a mixture of plutonium isotopes. A campaign with uranium oxide (UOX) fuel is also modeled to compare the neutronic characteristics with those of the MOX variant. For both MOX and UOX options, the efficiency of fuel use is analyzed at an increase in the water/fuel ratio (W/F) in comparison with the base case. The W/F ratio increases in three ways. For calculated estimates, the KASSETA-BIPR-7 software package is used. The results of calculations of individual neutronic characteristics with 100% MOX fuel when modeling the VVER-TOI variant with power of 3300 MW(t) are presented to compare with the results of calculations using other independent codes. |
| doi_str_mv | 10.1134/S1063778823080148 |
| format | Article |
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238
U and 0.2%
235
U) and a mixture of plutonium isotopes. A campaign with uranium oxide (UOX) fuel is also modeled to compare the neutronic characteristics with those of the MOX variant. For both MOX and UOX options, the efficiency of fuel use is analyzed at an increase in the water/fuel ratio (W/F) in comparison with the base case. The W/F ratio increases in three ways. For calculated estimates, the KASSETA-BIPR-7 software package is used. The results of calculations of individual neutronic characteristics with 100% MOX fuel when modeling the VVER-TOI variant with power of 3300 MW(t) are presented to compare with the results of calculations using other independent codes.</description><identifier>ISSN: 1063-7788</identifier><identifier>EISSN: 1562-692X</identifier><identifier>DOI: 10.1134/S1063778823080148</identifier><language>eng</language><publisher>Moscow: Pleiades Publishing</publisher><subject>Analysis ; Assemblies ; Fuels ; Mixed oxides ; MOX ; Nuclear energy ; Nuclear fuels ; Particle and Nuclear Physics ; Physics ; Physics and Astronomy ; Plutonium ; Plutonium isotopes ; Uranium ; Uranium oxides</subject><ispartof>Physics of atomic nuclei, 2023-12, Vol.86 (8), p.1856-1862</ispartof><rights>Pleiades Publishing, Ltd. 2023. ISSN 1063-7788, Physics of Atomic Nuclei, 2023, Vol. 86, No. 8, pp. 1856–1862. © Pleiades Publishing, Ltd., 2023. Russian Text © The Author(s), 2022, published in Voprosy Atomnoi Nauki i Tekhniki. Seriya: Fizika Yadernykh Reaktorov, 2022, No. 3, pp. 99–106.</rights><rights>COPYRIGHT 2023 Springer</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><cites>FETCH-LOGICAL-c341t-794475ea1dcd2f18e71972c01cc2d36f958c265cc9ac2c73e428f58d185d0aa43</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://link.springer.com/content/pdf/10.1134/S1063778823080148$$EPDF$$P50$$Gspringer$$H</linktopdf><linktohtml>$$Uhttps://link.springer.com/10.1134/S1063778823080148$$EHTML$$P50$$Gspringer$$H</linktohtml><link.rule.ids>315,781,785,27929,27930,41493,42562,51324</link.rule.ids></links><search><creatorcontrib>Trapeznikov, I. N.</creatorcontrib><creatorcontrib>Ponomarenko, G. L.</creatorcontrib><creatorcontrib>Vasilchenko, I. N.</creatorcontrib><title>Evaluation of the Possibility of Using the Full Load of MOX Fuel in the VVER-600 Reactor</title><title>Physics of atomic nuclei</title><addtitle>Phys. Atom. Nuclei</addtitle><description>In this paper, we analyze the possibility of using 100% MOX fuel (mixed oxide uranium-plutonium fuel) in a VVER-600 reactor with nominal power of 1600 MW(t). The VVER-600 core consists of 163 fuel assemblies (FAs) similar in design to VVER-TOI fuel assemblies. MOX fuel contains tailings of uranium (99.8%
238
U and 0.2%
235
U) and a mixture of plutonium isotopes. A campaign with uranium oxide (UOX) fuel is also modeled to compare the neutronic characteristics with those of the MOX variant. For both MOX and UOX options, the efficiency of fuel use is analyzed at an increase in the water/fuel ratio (W/F) in comparison with the base case. The W/F ratio increases in three ways. For calculated estimates, the KASSETA-BIPR-7 software package is used. The results of calculations of individual neutronic characteristics with 100% MOX fuel when modeling the VVER-TOI variant with power of 3300 MW(t) are presented to compare with the results of calculations using other independent codes.</description><subject>Analysis</subject><subject>Assemblies</subject><subject>Fuels</subject><subject>Mixed oxides</subject><subject>MOX</subject><subject>Nuclear energy</subject><subject>Nuclear fuels</subject><subject>Particle and Nuclear Physics</subject><subject>Physics</subject><subject>Physics and Astronomy</subject><subject>Plutonium</subject><subject>Plutonium isotopes</subject><subject>Uranium</subject><subject>Uranium oxides</subject><issn>1063-7788</issn><issn>1562-692X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2023</creationdate><recordtype>article</recordtype><recordid>eNp1kV1LwzAYhYsoOKc_wLuCV1505qMfyeUYmw4mk82N3ZWYJjWja2aSivv3pqsgQyQXCec8JznkDYJbCAYQ4vhhCUGKs4wQhAEBMCZnQQ8mKYpSijbn_uztqPUvgytrtwBASBLQCzbjT1Y1zCldh1qG7l2EL9pa9aYq5Q6ttLKqLo_GpKmqcKZZ0crP840XRBWq-miu1-NFlAIQLgTjTpvr4EKyyoqbn70frCbj19FTNJs_TkfDWcRxDF2U0TjOEsFgwQskIREZpBniAHKOCpxKmhCO0oRzyjjiGRYxIjIhhW9fAMZi3A_uunv3Rn80wrp8qxtT-ydzRBGlSUpx6qlBR5WsErmqpXaGcb8KsVNc10Iqrw8zghNIfAEfuD8JeMaJL1eyxtp8ulycsrBjufFfZ4TM90btmDnkEOTtdPI_0_EZ1GWsZ-tSmN_a_4e-AaGvjTM</recordid><startdate>20231201</startdate><enddate>20231201</enddate><creator>Trapeznikov, I. N.</creator><creator>Ponomarenko, G. L.</creator><creator>Vasilchenko, I. N.</creator><general>Pleiades Publishing</general><general>Springer</general><general>Springer Nature B.V</general><scope>AAYXX</scope><scope>CITATION</scope><scope>ISR</scope></search><sort><creationdate>20231201</creationdate><title>Evaluation of the Possibility of Using the Full Load of MOX Fuel in the VVER-600 Reactor</title><author>Trapeznikov, I. N. ; Ponomarenko, G. L. ; Vasilchenko, I. N.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c341t-794475ea1dcd2f18e71972c01cc2d36f958c265cc9ac2c73e428f58d185d0aa43</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2023</creationdate><topic>Analysis</topic><topic>Assemblies</topic><topic>Fuels</topic><topic>Mixed oxides</topic><topic>MOX</topic><topic>Nuclear energy</topic><topic>Nuclear fuels</topic><topic>Particle and Nuclear Physics</topic><topic>Physics</topic><topic>Physics and Astronomy</topic><topic>Plutonium</topic><topic>Plutonium isotopes</topic><topic>Uranium</topic><topic>Uranium oxides</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Trapeznikov, I. N.</creatorcontrib><creatorcontrib>Ponomarenko, G. L.</creatorcontrib><creatorcontrib>Vasilchenko, I. N.</creatorcontrib><collection>CrossRef</collection><collection>Gale In Context: Science</collection><jtitle>Physics of atomic nuclei</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Trapeznikov, I. N.</au><au>Ponomarenko, G. L.</au><au>Vasilchenko, I. N.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Evaluation of the Possibility of Using the Full Load of MOX Fuel in the VVER-600 Reactor</atitle><jtitle>Physics of atomic nuclei</jtitle><stitle>Phys. Atom. Nuclei</stitle><date>2023-12-01</date><risdate>2023</risdate><volume>86</volume><issue>8</issue><spage>1856</spage><epage>1862</epage><pages>1856-1862</pages><issn>1063-7788</issn><eissn>1562-692X</eissn><abstract>In this paper, we analyze the possibility of using 100% MOX fuel (mixed oxide uranium-plutonium fuel) in a VVER-600 reactor with nominal power of 1600 MW(t). The VVER-600 core consists of 163 fuel assemblies (FAs) similar in design to VVER-TOI fuel assemblies. MOX fuel contains tailings of uranium (99.8%
238
U and 0.2%
235
U) and a mixture of plutonium isotopes. A campaign with uranium oxide (UOX) fuel is also modeled to compare the neutronic characteristics with those of the MOX variant. For both MOX and UOX options, the efficiency of fuel use is analyzed at an increase in the water/fuel ratio (W/F) in comparison with the base case. The W/F ratio increases in three ways. For calculated estimates, the KASSETA-BIPR-7 software package is used. The results of calculations of individual neutronic characteristics with 100% MOX fuel when modeling the VVER-TOI variant with power of 3300 MW(t) are presented to compare with the results of calculations using other independent codes.</abstract><cop>Moscow</cop><pub>Pleiades Publishing</pub><doi>10.1134/S1063778823080148</doi><tpages>7</tpages></addata></record> |
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| source | Springer Nature - Complete Springer Journals |
| subjects | Analysis Assemblies Fuels Mixed oxides MOX Nuclear energy Nuclear fuels Particle and Nuclear Physics Physics Physics and Astronomy Plutonium Plutonium isotopes Uranium Uranium oxides |
| title | Evaluation of the Possibility of Using the Full Load of MOX Fuel in the VVER-600 Reactor |
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