Use of Microwave Radiation for Denitration of Uranyl Nitrate Solution and Subsequent Sintering of Uranium Dioxide Fuel Pellets
Fabrication of ceramic UO 2 fuel pellets using microwave radiation was studied. The UO 2 powder was prepared by microwave denitration of a nitric acid solution containing 400 g L –1 uranium. The tapped density (2.39 g cm –3 ) and total specific surface area (2.70 m 2 g –1 ) of the powder obtained me...
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| Veröffentlicht in: | Russian journal of applied chemistry 2021-03, Vol.94 (3), p.317-322 |
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| creator | Pilyushenko, K. S. Kulyako, Yu. M. Trofimov, T. I. Perevalov, S. A. Savel’ev, B. V. Vinokurov, S. E. Myasoedov, B. F. |
| description | Fabrication of ceramic UO
2
fuel pellets using microwave radiation was studied. The UO
2
powder was prepared by microwave denitration of a nitric acid solution containing 400 g L
–1
uranium. The tapped density (2.39 g cm
–3
) and total specific surface area (2.70 m
2
g
–1
) of the powder obtained met the requirements to the powder for nuclear fuel fabrication (TU (Technical Specification) 95 414–2005: Uranium Dioxide Powder of Ceramic Grade with the Uranium-235 Isotope Content Lower than 5.0%). Pellets were pressed from the UO
2
powder under varied conditions including pressure, its application mode, pressing time, and presence of binder. The pressed pellets were sintered at 1650°С for 2 h in an Ar + 10 vol % H
2
atmosphere under the action of microwave radiation. The density of the samples obtained, 10.40 ± 0.02 g cm
–3
, meets the requirements to ceramic fuel pellets used in thermal reactors. |
| doi_str_mv | 10.1134/S1070427221030071 |
| format | Article |
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2
fuel pellets using microwave radiation was studied. The UO
2
powder was prepared by microwave denitration of a nitric acid solution containing 400 g L
–1
uranium. The tapped density (2.39 g cm
–3
) and total specific surface area (2.70 m
2
g
–1
) of the powder obtained met the requirements to the powder for nuclear fuel fabrication (TU (Technical Specification) 95 414–2005: Uranium Dioxide Powder of Ceramic Grade with the Uranium-235 Isotope Content Lower than 5.0%). Pellets were pressed from the UO
2
powder under varied conditions including pressure, its application mode, pressing time, and presence of binder. The pressed pellets were sintered at 1650°С for 2 h in an Ar + 10 vol % H
2
atmosphere under the action of microwave radiation. The density of the samples obtained, 10.40 ± 0.02 g cm
–3
, meets the requirements to ceramic fuel pellets used in thermal reactors.</description><identifier>ISSN: 1070-4272</identifier><identifier>EISSN: 1608-3296</identifier><identifier>DOI: 10.1134/S1070427221030071</identifier><language>eng</language><publisher>Moscow: Pleiades Publishing</publisher><subject>Ceramic powders ; Ceramics ; Chemistry ; Chemistry and Materials Science ; Chemistry/Food Science ; Denitration ; Density ; Industrial Chemistry/Chemical Engineering ; Inorganic Synthesis and Industrial Inorganic Chemistry ; Microwaves ; Nitric acid ; Nuclear fuels ; Nuclear reactors ; Pellets ; Radiation ; Sintering (powder metallurgy) ; Thermal reactors ; Uranium ; Uranium dioxide</subject><ispartof>Russian journal of applied chemistry, 2021-03, Vol.94 (3), p.317-322</ispartof><rights>Pleiades Publishing, Ltd. 2021</rights><rights>Pleiades Publishing, Ltd. 2021.</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c353t-239e8278330c45228d2d0c69446f3c551b22ce4d210882cf0a98f2fef5fc3f463</citedby><cites>FETCH-LOGICAL-c353t-239e8278330c45228d2d0c69446f3c551b22ce4d210882cf0a98f2fef5fc3f463</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/S1070427221030071$$EPDF$$P50$$Gspringer$$H</linktopdf><linktohtml>$$Uhttps://link.springer.com/10.1134/S1070427221030071$$EHTML$$P50$$Gspringer$$H</linktohtml><link.rule.ids>314,776,780,27901,27902,41464,42533,51294</link.rule.ids></links><search><creatorcontrib>Pilyushenko, K. S.</creatorcontrib><creatorcontrib>Kulyako, Yu. M.</creatorcontrib><creatorcontrib>Trofimov, T. I.</creatorcontrib><creatorcontrib>Perevalov, S. A.</creatorcontrib><creatorcontrib>Savel’ev, B. V.</creatorcontrib><creatorcontrib>Vinokurov, S. E.</creatorcontrib><creatorcontrib>Myasoedov, B. F.</creatorcontrib><title>Use of Microwave Radiation for Denitration of Uranyl Nitrate Solution and Subsequent Sintering of Uranium Dioxide Fuel Pellets</title><title>Russian journal of applied chemistry</title><addtitle>Russ J Appl Chem</addtitle><description>Fabrication of ceramic UO
2
fuel pellets using microwave radiation was studied. The UO
2
powder was prepared by microwave denitration of a nitric acid solution containing 400 g L
–1
uranium. The tapped density (2.39 g cm
–3
) and total specific surface area (2.70 m
2
g
–1
) of the powder obtained met the requirements to the powder for nuclear fuel fabrication (TU (Technical Specification) 95 414–2005: Uranium Dioxide Powder of Ceramic Grade with the Uranium-235 Isotope Content Lower than 5.0%). Pellets were pressed from the UO
2
powder under varied conditions including pressure, its application mode, pressing time, and presence of binder. The pressed pellets were sintered at 1650°С for 2 h in an Ar + 10 vol % H
2
atmosphere under the action of microwave radiation. The density of the samples obtained, 10.40 ± 0.02 g cm
–3
, meets the requirements to ceramic fuel pellets used in thermal reactors.</description><subject>Ceramic powders</subject><subject>Ceramics</subject><subject>Chemistry</subject><subject>Chemistry and Materials Science</subject><subject>Chemistry/Food Science</subject><subject>Denitration</subject><subject>Density</subject><subject>Industrial Chemistry/Chemical Engineering</subject><subject>Inorganic Synthesis and Industrial Inorganic Chemistry</subject><subject>Microwaves</subject><subject>Nitric acid</subject><subject>Nuclear fuels</subject><subject>Nuclear reactors</subject><subject>Pellets</subject><subject>Radiation</subject><subject>Sintering (powder metallurgy)</subject><subject>Thermal reactors</subject><subject>Uranium</subject><subject>Uranium dioxide</subject><issn>1070-4272</issn><issn>1608-3296</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2021</creationdate><recordtype>article</recordtype><recordid>eNp1UMlOwzAUtBBIlMIHcLPEOeAtrnNELQWksojQc-Qmz8hV6hQ7AXrh23EbEAfE6S0z85ZB6JSSc0q5uMgpGRHBRoxRwgkZ0T00oJKohLNM7sc8wskWP0RHISwJIZmUaoA-5wFwY_CdLX3zrt8AP-nK6tY2DpvG4wk42_q-jrS5125T4_tdD3De1N0O0q7CebcI8NqBa3FuXQveupcfje1WeGKbD1sBnnZQ40eoa2jDMTowug5w8h2HaD69eh7fJLOH69vx5SwpecrbhPEMFBspzkkpUsZUxSpSykwIaXiZpnTBWAmiis8rxUpDdKYMM2BSU3IjJB-is37u2jfxxNAWy6bzLq4sWMppKqWgLLJoz4pehODBFGtvV9pvCkqKrc3FH5ujhvWasN4-DP538v-iL14ffyI</recordid><startdate>20210301</startdate><enddate>20210301</enddate><creator>Pilyushenko, K. S.</creator><creator>Kulyako, Yu. M.</creator><creator>Trofimov, T. I.</creator><creator>Perevalov, S. A.</creator><creator>Savel’ev, B. V.</creator><creator>Vinokurov, S. E.</creator><creator>Myasoedov, B. F.</creator><general>Pleiades Publishing</general><general>Springer Nature B.V</general><scope>AAYXX</scope><scope>CITATION</scope></search><sort><creationdate>20210301</creationdate><title>Use of Microwave Radiation for Denitration of Uranyl Nitrate Solution and Subsequent Sintering of Uranium Dioxide Fuel Pellets</title><author>Pilyushenko, K. S. ; Kulyako, Yu. M. ; Trofimov, T. I. ; Perevalov, S. A. ; Savel’ev, B. V. ; Vinokurov, S. E. ; Myasoedov, B. F.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c353t-239e8278330c45228d2d0c69446f3c551b22ce4d210882cf0a98f2fef5fc3f463</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2021</creationdate><topic>Ceramic powders</topic><topic>Ceramics</topic><topic>Chemistry</topic><topic>Chemistry and Materials Science</topic><topic>Chemistry/Food Science</topic><topic>Denitration</topic><topic>Density</topic><topic>Industrial Chemistry/Chemical Engineering</topic><topic>Inorganic Synthesis and Industrial Inorganic Chemistry</topic><topic>Microwaves</topic><topic>Nitric acid</topic><topic>Nuclear fuels</topic><topic>Nuclear reactors</topic><topic>Pellets</topic><topic>Radiation</topic><topic>Sintering (powder metallurgy)</topic><topic>Thermal reactors</topic><topic>Uranium</topic><topic>Uranium dioxide</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Pilyushenko, K. S.</creatorcontrib><creatorcontrib>Kulyako, Yu. M.</creatorcontrib><creatorcontrib>Trofimov, T. I.</creatorcontrib><creatorcontrib>Perevalov, S. A.</creatorcontrib><creatorcontrib>Savel’ev, B. V.</creatorcontrib><creatorcontrib>Vinokurov, S. E.</creatorcontrib><creatorcontrib>Myasoedov, B. F.</creatorcontrib><collection>CrossRef</collection><jtitle>Russian journal of applied chemistry</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Pilyushenko, K. S.</au><au>Kulyako, Yu. M.</au><au>Trofimov, T. I.</au><au>Perevalov, S. A.</au><au>Savel’ev, B. V.</au><au>Vinokurov, S. E.</au><au>Myasoedov, B. F.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Use of Microwave Radiation for Denitration of Uranyl Nitrate Solution and Subsequent Sintering of Uranium Dioxide Fuel Pellets</atitle><jtitle>Russian journal of applied chemistry</jtitle><stitle>Russ J Appl Chem</stitle><date>2021-03-01</date><risdate>2021</risdate><volume>94</volume><issue>3</issue><spage>317</spage><epage>322</epage><pages>317-322</pages><issn>1070-4272</issn><eissn>1608-3296</eissn><abstract>Fabrication of ceramic UO
2
fuel pellets using microwave radiation was studied. The UO
2
powder was prepared by microwave denitration of a nitric acid solution containing 400 g L
–1
uranium. The tapped density (2.39 g cm
–3
) and total specific surface area (2.70 m
2
g
–1
) of the powder obtained met the requirements to the powder for nuclear fuel fabrication (TU (Technical Specification) 95 414–2005: Uranium Dioxide Powder of Ceramic Grade with the Uranium-235 Isotope Content Lower than 5.0%). Pellets were pressed from the UO
2
powder under varied conditions including pressure, its application mode, pressing time, and presence of binder. The pressed pellets were sintered at 1650°С for 2 h in an Ar + 10 vol % H
2
atmosphere under the action of microwave radiation. The density of the samples obtained, 10.40 ± 0.02 g cm
–3
, meets the requirements to ceramic fuel pellets used in thermal reactors.</abstract><cop>Moscow</cop><pub>Pleiades Publishing</pub><doi>10.1134/S1070427221030071</doi><tpages>6</tpages></addata></record> |
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| ispartof | Russian journal of applied chemistry, 2021-03, Vol.94 (3), p.317-322 |
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| subjects | Ceramic powders Ceramics Chemistry Chemistry and Materials Science Chemistry/Food Science Denitration Density Industrial Chemistry/Chemical Engineering Inorganic Synthesis and Industrial Inorganic Chemistry Microwaves Nitric acid Nuclear fuels Nuclear reactors Pellets Radiation Sintering (powder metallurgy) Thermal reactors Uranium Uranium dioxide |
| title | Use of Microwave Radiation for Denitration of Uranyl Nitrate Solution and Subsequent Sintering of Uranium Dioxide Fuel Pellets |
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