Tokamak based hybrid systems for fuel production and recovery from spent nuclear fuel
The effect of the internal elements of a tokamak with different coolants on the transmutation rate of long-lived actinides is studied. The Monte Carlo method is used to calculate nuclear reactions in a homogeneous model of a blanket and in specific designs of a blanket. The neutron-physical calculat...
Ausführliche Beschreibung
Autor*in: |
Azizov, E. A. [verfasserIn] |
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Format: |
Artikel |
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Sprache: |
Englisch |
Erschienen: |
2011 |
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Schlagwörter: |
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Anmerkung: |
© Springer Science+Business Media, Inc. 2011 |
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Übergeordnetes Werk: |
Enthalten in: Atomic energy - Springer US, 1992, 110(2011), 2 vom: 25. Mai, Seite 93-98 |
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Übergeordnetes Werk: |
volume:110 ; year:2011 ; number:2 ; day:25 ; month:05 ; pages:93-98 |
Links: |
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DOI / URN: |
10.1007/s10512-011-9396-2 |
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OLC2060868645 |
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10.1007/s10512-011-9396-2 doi (DE-627)OLC2060868645 (DE-He213)s10512-011-9396-2-p DE-627 ger DE-627 rakwb eng 530 VZ Azizov, E. A. verfasserin aut Tokamak based hybrid systems for fuel production and recovery from spent nuclear fuel 2011 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media, Inc. 2011 The effect of the internal elements of a tokamak with different coolants on the transmutation rate of long-lived actinides is studied. The Monte Carlo method is used to calculate nuclear reactions in a homogeneous model of a blanket and in specific designs of a blanket. The neutron-physical calculations of a homogeneous model of a blanket showed that the absorption of neutrons by the central column of the tokamak and their moderation by the beryllium coating slow the transmutation rate to 35% of the initial value with the most efficient utilization of lead coolant. For water coolant, this effect is negligible. In a heterogeneous model of a blanket where water coolant is used, plutonium must be added to the actinides (50%/50%). The use of lead as the coolant will increase the transmutation rate of the actinides without using plutonium. In this case, it will be possible to reprocess spent nuclear fuel from more than 10 VVER-1000 in the JUST-T hybrid reactor. Plutonium Fuel Element Spend Nuclear Fuel Fissile Material Minor Actinide Gladush, G. G. aut Lopatkin, A. V. aut Lukasevich, I. B. aut Enthalten in Atomic energy Springer US, 1992 110(2011), 2 vom: 25. Mai, Seite 93-98 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:110 year:2011 number:2 day:25 month:05 pages:93-98 https://doi.org/10.1007/s10512-011-9396-2 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 AR 110 2011 2 25 05 93-98 |
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10.1007/s10512-011-9396-2 doi (DE-627)OLC2060868645 (DE-He213)s10512-011-9396-2-p DE-627 ger DE-627 rakwb eng 530 VZ Azizov, E. A. verfasserin aut Tokamak based hybrid systems for fuel production and recovery from spent nuclear fuel 2011 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media, Inc. 2011 The effect of the internal elements of a tokamak with different coolants on the transmutation rate of long-lived actinides is studied. The Monte Carlo method is used to calculate nuclear reactions in a homogeneous model of a blanket and in specific designs of a blanket. The neutron-physical calculations of a homogeneous model of a blanket showed that the absorption of neutrons by the central column of the tokamak and their moderation by the beryllium coating slow the transmutation rate to 35% of the initial value with the most efficient utilization of lead coolant. For water coolant, this effect is negligible. In a heterogeneous model of a blanket where water coolant is used, plutonium must be added to the actinides (50%/50%). The use of lead as the coolant will increase the transmutation rate of the actinides without using plutonium. In this case, it will be possible to reprocess spent nuclear fuel from more than 10 VVER-1000 in the JUST-T hybrid reactor. Plutonium Fuel Element Spend Nuclear Fuel Fissile Material Minor Actinide Gladush, G. G. aut Lopatkin, A. V. aut Lukasevich, I. B. aut Enthalten in Atomic energy Springer US, 1992 110(2011), 2 vom: 25. Mai, Seite 93-98 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:110 year:2011 number:2 day:25 month:05 pages:93-98 https://doi.org/10.1007/s10512-011-9396-2 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 AR 110 2011 2 25 05 93-98 |
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10.1007/s10512-011-9396-2 doi (DE-627)OLC2060868645 (DE-He213)s10512-011-9396-2-p DE-627 ger DE-627 rakwb eng 530 VZ Azizov, E. A. verfasserin aut Tokamak based hybrid systems for fuel production and recovery from spent nuclear fuel 2011 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media, Inc. 2011 The effect of the internal elements of a tokamak with different coolants on the transmutation rate of long-lived actinides is studied. The Monte Carlo method is used to calculate nuclear reactions in a homogeneous model of a blanket and in specific designs of a blanket. The neutron-physical calculations of a homogeneous model of a blanket showed that the absorption of neutrons by the central column of the tokamak and their moderation by the beryllium coating slow the transmutation rate to 35% of the initial value with the most efficient utilization of lead coolant. For water coolant, this effect is negligible. In a heterogeneous model of a blanket where water coolant is used, plutonium must be added to the actinides (50%/50%). The use of lead as the coolant will increase the transmutation rate of the actinides without using plutonium. In this case, it will be possible to reprocess spent nuclear fuel from more than 10 VVER-1000 in the JUST-T hybrid reactor. Plutonium Fuel Element Spend Nuclear Fuel Fissile Material Minor Actinide Gladush, G. G. aut Lopatkin, A. V. aut Lukasevich, I. B. aut Enthalten in Atomic energy Springer US, 1992 110(2011), 2 vom: 25. Mai, Seite 93-98 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:110 year:2011 number:2 day:25 month:05 pages:93-98 https://doi.org/10.1007/s10512-011-9396-2 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 AR 110 2011 2 25 05 93-98 |
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10.1007/s10512-011-9396-2 doi (DE-627)OLC2060868645 (DE-He213)s10512-011-9396-2-p DE-627 ger DE-627 rakwb eng 530 VZ Azizov, E. A. verfasserin aut Tokamak based hybrid systems for fuel production and recovery from spent nuclear fuel 2011 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media, Inc. 2011 The effect of the internal elements of a tokamak with different coolants on the transmutation rate of long-lived actinides is studied. The Monte Carlo method is used to calculate nuclear reactions in a homogeneous model of a blanket and in specific designs of a blanket. The neutron-physical calculations of a homogeneous model of a blanket showed that the absorption of neutrons by the central column of the tokamak and their moderation by the beryllium coating slow the transmutation rate to 35% of the initial value with the most efficient utilization of lead coolant. For water coolant, this effect is negligible. In a heterogeneous model of a blanket where water coolant is used, plutonium must be added to the actinides (50%/50%). The use of lead as the coolant will increase the transmutation rate of the actinides without using plutonium. In this case, it will be possible to reprocess spent nuclear fuel from more than 10 VVER-1000 in the JUST-T hybrid reactor. Plutonium Fuel Element Spend Nuclear Fuel Fissile Material Minor Actinide Gladush, G. G. aut Lopatkin, A. V. aut Lukasevich, I. B. aut Enthalten in Atomic energy Springer US, 1992 110(2011), 2 vom: 25. Mai, Seite 93-98 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:110 year:2011 number:2 day:25 month:05 pages:93-98 https://doi.org/10.1007/s10512-011-9396-2 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 AR 110 2011 2 25 05 93-98 |
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10.1007/s10512-011-9396-2 doi (DE-627)OLC2060868645 (DE-He213)s10512-011-9396-2-p DE-627 ger DE-627 rakwb eng 530 VZ Azizov, E. A. verfasserin aut Tokamak based hybrid systems for fuel production and recovery from spent nuclear fuel 2011 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media, Inc. 2011 The effect of the internal elements of a tokamak with different coolants on the transmutation rate of long-lived actinides is studied. The Monte Carlo method is used to calculate nuclear reactions in a homogeneous model of a blanket and in specific designs of a blanket. The neutron-physical calculations of a homogeneous model of a blanket showed that the absorption of neutrons by the central column of the tokamak and their moderation by the beryllium coating slow the transmutation rate to 35% of the initial value with the most efficient utilization of lead coolant. For water coolant, this effect is negligible. In a heterogeneous model of a blanket where water coolant is used, plutonium must be added to the actinides (50%/50%). The use of lead as the coolant will increase the transmutation rate of the actinides without using plutonium. In this case, it will be possible to reprocess spent nuclear fuel from more than 10 VVER-1000 in the JUST-T hybrid reactor. Plutonium Fuel Element Spend Nuclear Fuel Fissile Material Minor Actinide Gladush, G. G. aut Lopatkin, A. V. aut Lukasevich, I. B. aut Enthalten in Atomic energy Springer US, 1992 110(2011), 2 vom: 25. Mai, Seite 93-98 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:110 year:2011 number:2 day:25 month:05 pages:93-98 https://doi.org/10.1007/s10512-011-9396-2 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 AR 110 2011 2 25 05 93-98 |
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abstract |
The effect of the internal elements of a tokamak with different coolants on the transmutation rate of long-lived actinides is studied. The Monte Carlo method is used to calculate nuclear reactions in a homogeneous model of a blanket and in specific designs of a blanket. The neutron-physical calculations of a homogeneous model of a blanket showed that the absorption of neutrons by the central column of the tokamak and their moderation by the beryllium coating slow the transmutation rate to 35% of the initial value with the most efficient utilization of lead coolant. For water coolant, this effect is negligible. In a heterogeneous model of a blanket where water coolant is used, plutonium must be added to the actinides (50%/50%). The use of lead as the coolant will increase the transmutation rate of the actinides without using plutonium. In this case, it will be possible to reprocess spent nuclear fuel from more than 10 VVER-1000 in the JUST-T hybrid reactor. © Springer Science+Business Media, Inc. 2011 |
abstractGer |
The effect of the internal elements of a tokamak with different coolants on the transmutation rate of long-lived actinides is studied. The Monte Carlo method is used to calculate nuclear reactions in a homogeneous model of a blanket and in specific designs of a blanket. The neutron-physical calculations of a homogeneous model of a blanket showed that the absorption of neutrons by the central column of the tokamak and their moderation by the beryllium coating slow the transmutation rate to 35% of the initial value with the most efficient utilization of lead coolant. For water coolant, this effect is negligible. In a heterogeneous model of a blanket where water coolant is used, plutonium must be added to the actinides (50%/50%). The use of lead as the coolant will increase the transmutation rate of the actinides without using plutonium. In this case, it will be possible to reprocess spent nuclear fuel from more than 10 VVER-1000 in the JUST-T hybrid reactor. © Springer Science+Business Media, Inc. 2011 |
abstract_unstemmed |
The effect of the internal elements of a tokamak with different coolants on the transmutation rate of long-lived actinides is studied. The Monte Carlo method is used to calculate nuclear reactions in a homogeneous model of a blanket and in specific designs of a blanket. The neutron-physical calculations of a homogeneous model of a blanket showed that the absorption of neutrons by the central column of the tokamak and their moderation by the beryllium coating slow the transmutation rate to 35% of the initial value with the most efficient utilization of lead coolant. For water coolant, this effect is negligible. In a heterogeneous model of a blanket where water coolant is used, plutonium must be added to the actinides (50%/50%). The use of lead as the coolant will increase the transmutation rate of the actinides without using plutonium. In this case, it will be possible to reprocess spent nuclear fuel from more than 10 VVER-1000 in the JUST-T hybrid reactor. © Springer Science+Business Media, Inc. 2011 |
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Tokamak based hybrid systems for fuel production and recovery from spent nuclear fuel |
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https://doi.org/10.1007/s10512-011-9396-2 |
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author2 |
Gladush, G. G. Lopatkin, A. V. Lukasevich, I. B. |
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Gladush, G. G. Lopatkin, A. V. Lukasevich, I. B. |
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17102916X |
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doi_str |
10.1007/s10512-011-9396-2 |
up_date |
2024-07-04T02:21:02.787Z |
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1803613280966541312 |
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