Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel

Abstract The process of uranium reduction via plasma denitration of uranyl nitrate solutions in a plasma reactor of a nuclear-safe geometry with the use of soluble reducing agents (carbamide ($ NH_{2} $)2CO, sucrose $ C_{12} %$ H_{22} %$ O_{11} $, and acetic acid $ CH_{3} $COOH) is studied. Disperse...
Ausführliche Beschreibung

Gespeichert in:

Autor*in:	Tumanov, Yu. N. [verfasserIn] Dedov, N. V.

Format:	E-Artikel
Sprache:	Englisch

Erschienen:	2015

Schlagwörter:	plasma denitration uranyl nitrate plutonium oxides soluble reducing agent carbamide sucrose acetic acid oxygen coefficient pyrophoricity technical and economic assessment

Anmerkung:	© Pleiades Publishing, Ltd. 2015

Übergeordnetes Werk:	Enthalten in: Inorganic materials - Dordrecht [u.a.] : Springer Science + Business Media B.V, 2010, 6(2015), 3 vom: Mai, Seite 205-211
Übergeordnetes Werk:	volume:6 ; year:2015 ; number:3 ; month:05 ; pages:205-211

Links:	Volltext

DOI / URN:	10.1134/S2075113315030120

Katalog-ID:	SPR030783836

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520			\|a Abstract The process of uranium reduction via plasma denitration of uranyl nitrate solutions in a plasma reactor of a nuclear-safe geometry with the use of soluble reducing agents (carbamide ($ NH_{2} $)2CO, sucrose $ C_{12} %$ H_{22} %$ O_{11} $, and acetic acid $ CH_{3} $COOH) is studied. Dispersed uranium oxide with the required oxygen coefficient (2.1–2.3) is obtained. It is found that acetic acid is the optimum reducing agent, and the optimum mass ratio HAc/U is 0.5–0.6. It is demonstrated that the synthesis of uranium oxides by the plasma denitration method is economically more viable than the mainstream technology.
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allfields	10.1134/S2075113315030120 doi (DE-627)SPR030783836 (SPR)S2075113315030120-e DE-627 ger DE-627 rakwb eng Tumanov, Yu. N. verfasserin aut Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel 2015 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier © Pleiades Publishing, Ltd. 2015 Abstract The process of uranium reduction via plasma denitration of uranyl nitrate solutions in a plasma reactor of a nuclear-safe geometry with the use of soluble reducing agents (carbamide ($ NH_{2} $)2CO, sucrose $ C_{12} %$ H_{22} %$ O_{11} $, and acetic acid $ CH_{3} $COOH) is studied. Dispersed uranium oxide with the required oxygen coefficient (2.1–2.3) is obtained. It is found that acetic acid is the optimum reducing agent, and the optimum mass ratio HAc/U is 0.5–0.6. It is demonstrated that the synthesis of uranium oxides by the plasma denitration method is economically more viable than the mainstream technology. plasma denitration (dpeaa)DE-He213 uranyl nitrate (dpeaa)DE-He213 plutonium (dpeaa)DE-He213 oxides (dpeaa)DE-He213 soluble reducing agent (dpeaa)DE-He213 carbamide (dpeaa)DE-He213 sucrose (dpeaa)DE-He213 acetic acid (dpeaa)DE-He213 oxygen coefficient (dpeaa)DE-He213 pyrophoricity (dpeaa)DE-He213 technical and economic assessment (dpeaa)DE-He213 Dedov, N. V. aut Enthalten in Inorganic materials Dordrecht [u.a.] : Springer Science + Business Media B.V, 2010 6(2015), 3 vom: Mai, Seite 205-211 (DE-627)624822788 (DE-600)2549876-9 2075-115X nnns volume:6 year:2015 number:3 month:05 pages:205-211 https://dx.doi.org/10.1134/S2075113315030120 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER SSG-OLC-PHA GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2070 GBV_ILN_2086 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2116 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 AR 6 2015 3 05 205-211
spelling	10.1134/S2075113315030120 doi (DE-627)SPR030783836 (SPR)S2075113315030120-e DE-627 ger DE-627 rakwb eng Tumanov, Yu. N. verfasserin aut Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel 2015 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier © Pleiades Publishing, Ltd. 2015 Abstract The process of uranium reduction via plasma denitration of uranyl nitrate solutions in a plasma reactor of a nuclear-safe geometry with the use of soluble reducing agents (carbamide ($ NH_{2} $)2CO, sucrose $ C_{12} %$ H_{22} %$ O_{11} $, and acetic acid $ CH_{3} $COOH) is studied. Dispersed uranium oxide with the required oxygen coefficient (2.1–2.3) is obtained. It is found that acetic acid is the optimum reducing agent, and the optimum mass ratio HAc/U is 0.5–0.6. It is demonstrated that the synthesis of uranium oxides by the plasma denitration method is economically more viable than the mainstream technology. plasma denitration (dpeaa)DE-He213 uranyl nitrate (dpeaa)DE-He213 plutonium (dpeaa)DE-He213 oxides (dpeaa)DE-He213 soluble reducing agent (dpeaa)DE-He213 carbamide (dpeaa)DE-He213 sucrose (dpeaa)DE-He213 acetic acid (dpeaa)DE-He213 oxygen coefficient (dpeaa)DE-He213 pyrophoricity (dpeaa)DE-He213 technical and economic assessment (dpeaa)DE-He213 Dedov, N. V. aut Enthalten in Inorganic materials Dordrecht [u.a.] : Springer Science + Business Media B.V, 2010 6(2015), 3 vom: Mai, Seite 205-211 (DE-627)624822788 (DE-600)2549876-9 2075-115X nnns volume:6 year:2015 number:3 month:05 pages:205-211 https://dx.doi.org/10.1134/S2075113315030120 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER SSG-OLC-PHA GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2070 GBV_ILN_2086 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2116 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 AR 6 2015 3 05 205-211
allfields_unstemmed	10.1134/S2075113315030120 doi (DE-627)SPR030783836 (SPR)S2075113315030120-e DE-627 ger DE-627 rakwb eng Tumanov, Yu. N. verfasserin aut Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel 2015 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier © Pleiades Publishing, Ltd. 2015 Abstract The process of uranium reduction via plasma denitration of uranyl nitrate solutions in a plasma reactor of a nuclear-safe geometry with the use of soluble reducing agents (carbamide ($ NH_{2} $)2CO, sucrose $ C_{12} %$ H_{22} %$ O_{11} $, and acetic acid $ CH_{3} $COOH) is studied. Dispersed uranium oxide with the required oxygen coefficient (2.1–2.3) is obtained. It is found that acetic acid is the optimum reducing agent, and the optimum mass ratio HAc/U is 0.5–0.6. It is demonstrated that the synthesis of uranium oxides by the plasma denitration method is economically more viable than the mainstream technology. plasma denitration (dpeaa)DE-He213 uranyl nitrate (dpeaa)DE-He213 plutonium (dpeaa)DE-He213 oxides (dpeaa)DE-He213 soluble reducing agent (dpeaa)DE-He213 carbamide (dpeaa)DE-He213 sucrose (dpeaa)DE-He213 acetic acid (dpeaa)DE-He213 oxygen coefficient (dpeaa)DE-He213 pyrophoricity (dpeaa)DE-He213 technical and economic assessment (dpeaa)DE-He213 Dedov, N. V. aut Enthalten in Inorganic materials Dordrecht [u.a.] : Springer Science + Business Media B.V, 2010 6(2015), 3 vom: Mai, Seite 205-211 (DE-627)624822788 (DE-600)2549876-9 2075-115X nnns volume:6 year:2015 number:3 month:05 pages:205-211 https://dx.doi.org/10.1134/S2075113315030120 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER SSG-OLC-PHA GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2070 GBV_ILN_2086 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2116 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 AR 6 2015 3 05 205-211
allfieldsGer	10.1134/S2075113315030120 doi (DE-627)SPR030783836 (SPR)S2075113315030120-e DE-627 ger DE-627 rakwb eng Tumanov, Yu. N. verfasserin aut Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel 2015 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier © Pleiades Publishing, Ltd. 2015 Abstract The process of uranium reduction via plasma denitration of uranyl nitrate solutions in a plasma reactor of a nuclear-safe geometry with the use of soluble reducing agents (carbamide ($ NH_{2} $)2CO, sucrose $ C_{12} %$ H_{22} %$ O_{11} $, and acetic acid $ CH_{3} $COOH) is studied. Dispersed uranium oxide with the required oxygen coefficient (2.1–2.3) is obtained. It is found that acetic acid is the optimum reducing agent, and the optimum mass ratio HAc/U is 0.5–0.6. It is demonstrated that the synthesis of uranium oxides by the plasma denitration method is economically more viable than the mainstream technology. plasma denitration (dpeaa)DE-He213 uranyl nitrate (dpeaa)DE-He213 plutonium (dpeaa)DE-He213 oxides (dpeaa)DE-He213 soluble reducing agent (dpeaa)DE-He213 carbamide (dpeaa)DE-He213 sucrose (dpeaa)DE-He213 acetic acid (dpeaa)DE-He213 oxygen coefficient (dpeaa)DE-He213 pyrophoricity (dpeaa)DE-He213 technical and economic assessment (dpeaa)DE-He213 Dedov, N. V. aut Enthalten in Inorganic materials Dordrecht [u.a.] : Springer Science + Business Media B.V, 2010 6(2015), 3 vom: Mai, Seite 205-211 (DE-627)624822788 (DE-600)2549876-9 2075-115X nnns volume:6 year:2015 number:3 month:05 pages:205-211 https://dx.doi.org/10.1134/S2075113315030120 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER SSG-OLC-PHA GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2070 GBV_ILN_2086 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2116 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 AR 6 2015 3 05 205-211
allfieldsSound	10.1134/S2075113315030120 doi (DE-627)SPR030783836 (SPR)S2075113315030120-e DE-627 ger DE-627 rakwb eng Tumanov, Yu. N. verfasserin aut Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel 2015 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier © Pleiades Publishing, Ltd. 2015 Abstract The process of uranium reduction via plasma denitration of uranyl nitrate solutions in a plasma reactor of a nuclear-safe geometry with the use of soluble reducing agents (carbamide ($ NH_{2} $)2CO, sucrose $ C_{12} %$ H_{22} %$ O_{11} $, and acetic acid $ CH_{3} $COOH) is studied. Dispersed uranium oxide with the required oxygen coefficient (2.1–2.3) is obtained. It is found that acetic acid is the optimum reducing agent, and the optimum mass ratio HAc/U is 0.5–0.6. It is demonstrated that the synthesis of uranium oxides by the plasma denitration method is economically more viable than the mainstream technology. plasma denitration (dpeaa)DE-He213 uranyl nitrate (dpeaa)DE-He213 plutonium (dpeaa)DE-He213 oxides (dpeaa)DE-He213 soluble reducing agent (dpeaa)DE-He213 carbamide (dpeaa)DE-He213 sucrose (dpeaa)DE-He213 acetic acid (dpeaa)DE-He213 oxygen coefficient (dpeaa)DE-He213 pyrophoricity (dpeaa)DE-He213 technical and economic assessment (dpeaa)DE-He213 Dedov, N. V. aut Enthalten in Inorganic materials Dordrecht [u.a.] : Springer Science + Business Media B.V, 2010 6(2015), 3 vom: Mai, Seite 205-211 (DE-627)624822788 (DE-600)2549876-9 2075-115X nnns volume:6 year:2015 number:3 month:05 pages:205-211 https://dx.doi.org/10.1134/S2075113315030120 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER SSG-OLC-PHA GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2070 GBV_ILN_2086 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2116 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 AR 6 2015 3 05 205-211
language	English
source	Enthalten in Inorganic materials 6(2015), 3 vom: Mai, Seite 205-211 volume:6 year:2015 number:3 month:05 pages:205-211
sourceStr	Enthalten in Inorganic materials 6(2015), 3 vom: Mai, Seite 205-211 volume:6 year:2015 number:3 month:05 pages:205-211
format_phy_str_mv	Article
institution	findex.gbv.de
topic_facet	plasma denitration uranyl nitrate plutonium oxides soluble reducing agent carbamide sucrose acetic acid oxygen coefficient pyrophoricity technical and economic assessment
isfreeaccess_bool	false
container_title	Inorganic materials
authorswithroles_txt_mv	Tumanov, Yu. N. @@aut@@ Dedov, N. V. @@aut@@
publishDateDaySort_date	2015-05-01T00:00:00Z
hierarchy_top_id	624822788
id	SPR030783836
language_de	englisch
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N.</subfield><subfield code="e">verfasserin</subfield><subfield code="4">aut</subfield></datafield><datafield tag="245" ind1="1" ind2="0"><subfield code="a">Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel</subfield></datafield><datafield tag="264" ind1=" " ind2="1"><subfield code="c">2015</subfield></datafield><datafield tag="336" ind1=" " ind2=" "><subfield code="a">Text</subfield><subfield code="b">txt</subfield><subfield code="2">rdacontent</subfield></datafield><datafield tag="337" ind1=" " ind2=" "><subfield code="a">Computermedien</subfield><subfield code="b">c</subfield><subfield code="2">rdamedia</subfield></datafield><datafield tag="338" ind1=" " ind2=" "><subfield code="a">Online-Ressource</subfield><subfield code="b">cr</subfield><subfield code="2">rdacarrier</subfield></datafield><datafield tag="500" ind1=" " ind2=" "><subfield code="a">© Pleiades Publishing, Ltd. 2015</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="a">Abstract The process of uranium reduction via plasma denitration of uranyl nitrate solutions in a plasma reactor of a nuclear-safe geometry with the use of soluble reducing agents (carbamide ($ NH_{2} $)2CO, sucrose $ C_{12} %$ H_{22} %$ O_{11} $, and acetic acid $ CH_{3} $COOH) is studied. Dispersed uranium oxide with the required oxygen coefficient (2.1–2.3) is obtained. It is found that acetic acid is the optimum reducing agent, and the optimum mass ratio HAc/U is 0.5–0.6. 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author	Tumanov, Yu. N.
spellingShingle	Tumanov, Yu. N. misc plasma denitration misc uranyl nitrate misc plutonium misc oxides misc soluble reducing agent misc carbamide misc sucrose misc acetic acid misc oxygen coefficient misc pyrophoricity misc technical and economic assessment Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel
authorStr	Tumanov, Yu. N.
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topic_title	Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel plasma denitration (dpeaa)DE-He213 uranyl nitrate (dpeaa)DE-He213 plutonium (dpeaa)DE-He213 oxides (dpeaa)DE-He213 soluble reducing agent (dpeaa)DE-He213 carbamide (dpeaa)DE-He213 sucrose (dpeaa)DE-He213 acetic acid (dpeaa)DE-He213 oxygen coefficient (dpeaa)DE-He213 pyrophoricity (dpeaa)DE-He213 technical and economic assessment (dpeaa)DE-He213
topic	misc plasma denitration misc uranyl nitrate misc plutonium misc oxides misc soluble reducing agent misc carbamide misc sucrose misc acetic acid misc oxygen coefficient misc pyrophoricity misc technical and economic assessment
topic_unstemmed	misc plasma denitration misc uranyl nitrate misc plutonium misc oxides misc soluble reducing agent misc carbamide misc sucrose misc acetic acid misc oxygen coefficient misc pyrophoricity misc technical and economic assessment
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title	Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel
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title_full	Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel
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author-letter	Tumanov, Yu. N.
doi_str_mv	10.1134/S2075113315030120
title_sort	development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel
title_auth	Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel
abstract	Abstract The process of uranium reduction via plasma denitration of uranyl nitrate solutions in a plasma reactor of a nuclear-safe geometry with the use of soluble reducing agents (carbamide ($ NH_{2} $)2CO, sucrose $ C_{12} %$ H_{22} %$ O_{11} $, and acetic acid $ CH_{3} $COOH) is studied. Dispersed uranium oxide with the required oxygen coefficient (2.1–2.3) is obtained. It is found that acetic acid is the optimum reducing agent, and the optimum mass ratio HAc/U is 0.5–0.6. It is demonstrated that the synthesis of uranium oxides by the plasma denitration method is economically more viable than the mainstream technology. © Pleiades Publishing, Ltd. 2015
abstractGer	Abstract The process of uranium reduction via plasma denitration of uranyl nitrate solutions in a plasma reactor of a nuclear-safe geometry with the use of soluble reducing agents (carbamide ($ NH_{2} $)2CO, sucrose $ C_{12} %$ H_{22} %$ O_{11} $, and acetic acid $ CH_{3} $COOH) is studied. Dispersed uranium oxide with the required oxygen coefficient (2.1–2.3) is obtained. It is found that acetic acid is the optimum reducing agent, and the optimum mass ratio HAc/U is 0.5–0.6. It is demonstrated that the synthesis of uranium oxides by the plasma denitration method is economically more viable than the mainstream technology. © Pleiades Publishing, Ltd. 2015
abstract_unstemmed	Abstract The process of uranium reduction via plasma denitration of uranyl nitrate solutions in a plasma reactor of a nuclear-safe geometry with the use of soluble reducing agents (carbamide ($ NH_{2} $)2CO, sucrose $ C_{12} %$ H_{22} %$ O_{11} $, and acetic acid $ CH_{3} $COOH) is studied. Dispersed uranium oxide with the required oxygen coefficient (2.1–2.3) is obtained. It is found that acetic acid is the optimum reducing agent, and the optimum mass ratio HAc/U is 0.5–0.6. It is demonstrated that the synthesis of uranium oxides by the plasma denitration method is economically more viable than the mainstream technology. © Pleiades Publishing, Ltd. 2015
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container_issue	3
title_short	Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel
url	https://dx.doi.org/10.1134/S2075113315030120
remote_bool	true
author2	Dedov, N. V.
author2Str	Dedov, N. V.
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doi_str	10.1134/S2075113315030120
up_date	2024-07-03T20:07:04.058Z
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score	7.399131

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Development of the plasma technology for the production of uranium oxides with a given oxygen coefficient for the fabrication of pelletized nuclear fuel

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Vorhandene Bände

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