Analysis of the Possibilities of Developing a Molten-Salt Blanket for a Subcritical Demonstration Reactor
The possibilities of developing a demonstration electronuclear facility with a subcritical reactor, proton accelerator and neutron source in the form of a target unit are analyzed. This facility is proposed for working out key technologies for utilizing Np, Am, and Cm obtained from spent nuclear fue...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Nevinitsa, V. A. [verfasserIn] |
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| Format: |
Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2014 |
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| Schlagwörter: |
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| Anmerkung: |
© Springer Science+Business Media New York 2014 |
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| Übergeordnetes Werk: |
Enthalten in: Atomic energy - Springer US, 1992, 117(2014), 1 vom: 14. Okt., Seite 14-18 |
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| Übergeordnetes Werk: |
volume:117 ; year:2014 ; number:1 ; day:14 ; month:10 ; pages:14-18 |
| Links: |
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| DOI / URN: |
10.1007/s10512-014-9881-5 |
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| Katalog-ID: |
OLC2060873215 |
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| 520 | |a The possibilities of developing a demonstration electronuclear facility with a subcritical reactor, proton accelerator and neutron source in the form of a target unit are analyzed. This facility is proposed for working out key technologies for utilizing Np, Am, and Cm obtained from spent nuclear fuel as well as the production of 233U and 233Pa in the blanket of a molten-salt reactor. The transmutation technologies are important for bringing the raw isotopes 238U and 232Th into energy production, closing the nuclear fuel cycle, reducing the amounts of buried transuranium elements, and increasing the nuclear fuel utilization efficiency. | ||
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| 700 | 1 | |a Sedov, A. A. |4 aut | |
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| 700 | 1 | |a Subbotin, A. S. |4 aut | |
| 700 | 1 | |a Subbotin, S. A. |4 aut | |
| 700 | 1 | |a Alekseev, P. N. |4 aut | |
| 700 | 1 | |a Voloshchenko, A. M. |4 aut | |
| 700 | 1 | |a Titarenko, Yu. E. |4 aut | |
| 700 | 1 | |a Batyaev, V. F. |4 aut | |
| 700 | 1 | |a Rogov, V. I. |4 aut | |
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10.1007/s10512-014-9881-5 doi (DE-627)OLC2060873215 (DE-He213)s10512-014-9881-5-p DE-627 ger DE-627 rakwb eng 530 VZ Nevinitsa, V. A. verfasserin aut Analysis of the Possibilities of Developing a Molten-Salt Blanket for a Subcritical Demonstration Reactor 2014 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media New York 2014 The possibilities of developing a demonstration electronuclear facility with a subcritical reactor, proton accelerator and neutron source in the form of a target unit are analyzed. This facility is proposed for working out key technologies for utilizing Np, Am, and Cm obtained from spent nuclear fuel as well as the production of 233U and 233Pa in the blanket of a molten-salt reactor. The transmutation technologies are important for bringing the raw isotopes 238U and 232Th into energy production, closing the nuclear fuel cycle, reducing the amounts of buried transuranium elements, and increasing the nuclear fuel utilization efficiency. Thorium Fuel Cycle Spend Fuel Spend Nuclear Fuel Nuclear Fuel Cycle Dudnikov, A. A. aut Frolov, A. A. aut Lubina, A. S. aut Sedov, A. A. aut Blandinskii, V. Yu. aut Balanin, A. L. aut Belov, I. A. aut Fomichenko, P. A. aut Subbotin, A. S. aut Subbotin, S. A. aut Alekseev, P. N. aut Voloshchenko, A. M. aut Titarenko, Yu. E. aut Batyaev, V. F. aut Rogov, V. I. aut Pavlov, K. V. aut Titarenko, A. Yu. aut Kulevoy, T. V. aut Gerasimov, K. A. aut Didenko, A. N. aut Polozov, S. M. aut Enthalten in Atomic energy Springer US, 1992 117(2014), 1 vom: 14. Okt., Seite 14-18 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:117 year:2014 number:1 day:14 month:10 pages:14-18 https://doi.org/10.1007/s10512-014-9881-5 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 AR 117 2014 1 14 10 14-18 |
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10.1007/s10512-014-9881-5 doi (DE-627)OLC2060873215 (DE-He213)s10512-014-9881-5-p DE-627 ger DE-627 rakwb eng 530 VZ Nevinitsa, V. A. verfasserin aut Analysis of the Possibilities of Developing a Molten-Salt Blanket for a Subcritical Demonstration Reactor 2014 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media New York 2014 The possibilities of developing a demonstration electronuclear facility with a subcritical reactor, proton accelerator and neutron source in the form of a target unit are analyzed. This facility is proposed for working out key technologies for utilizing Np, Am, and Cm obtained from spent nuclear fuel as well as the production of 233U and 233Pa in the blanket of a molten-salt reactor. The transmutation technologies are important for bringing the raw isotopes 238U and 232Th into energy production, closing the nuclear fuel cycle, reducing the amounts of buried transuranium elements, and increasing the nuclear fuel utilization efficiency. Thorium Fuel Cycle Spend Fuel Spend Nuclear Fuel Nuclear Fuel Cycle Dudnikov, A. A. aut Frolov, A. A. aut Lubina, A. S. aut Sedov, A. A. aut Blandinskii, V. Yu. aut Balanin, A. L. aut Belov, I. A. aut Fomichenko, P. A. aut Subbotin, A. S. aut Subbotin, S. A. aut Alekseev, P. N. aut Voloshchenko, A. M. aut Titarenko, Yu. E. aut Batyaev, V. F. aut Rogov, V. I. aut Pavlov, K. V. aut Titarenko, A. Yu. aut Kulevoy, T. V. aut Gerasimov, K. A. aut Didenko, A. N. aut Polozov, S. M. aut Enthalten in Atomic energy Springer US, 1992 117(2014), 1 vom: 14. Okt., Seite 14-18 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:117 year:2014 number:1 day:14 month:10 pages:14-18 https://doi.org/10.1007/s10512-014-9881-5 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 AR 117 2014 1 14 10 14-18 |
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10.1007/s10512-014-9881-5 doi (DE-627)OLC2060873215 (DE-He213)s10512-014-9881-5-p DE-627 ger DE-627 rakwb eng 530 VZ Nevinitsa, V. A. verfasserin aut Analysis of the Possibilities of Developing a Molten-Salt Blanket for a Subcritical Demonstration Reactor 2014 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media New York 2014 The possibilities of developing a demonstration electronuclear facility with a subcritical reactor, proton accelerator and neutron source in the form of a target unit are analyzed. This facility is proposed for working out key technologies for utilizing Np, Am, and Cm obtained from spent nuclear fuel as well as the production of 233U and 233Pa in the blanket of a molten-salt reactor. The transmutation technologies are important for bringing the raw isotopes 238U and 232Th into energy production, closing the nuclear fuel cycle, reducing the amounts of buried transuranium elements, and increasing the nuclear fuel utilization efficiency. Thorium Fuel Cycle Spend Fuel Spend Nuclear Fuel Nuclear Fuel Cycle Dudnikov, A. A. aut Frolov, A. A. aut Lubina, A. S. aut Sedov, A. A. aut Blandinskii, V. Yu. aut Balanin, A. L. aut Belov, I. A. aut Fomichenko, P. A. aut Subbotin, A. S. aut Subbotin, S. A. aut Alekseev, P. N. aut Voloshchenko, A. M. aut Titarenko, Yu. E. aut Batyaev, V. F. aut Rogov, V. I. aut Pavlov, K. V. aut Titarenko, A. Yu. aut Kulevoy, T. V. aut Gerasimov, K. A. aut Didenko, A. N. aut Polozov, S. M. aut Enthalten in Atomic energy Springer US, 1992 117(2014), 1 vom: 14. Okt., Seite 14-18 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:117 year:2014 number:1 day:14 month:10 pages:14-18 https://doi.org/10.1007/s10512-014-9881-5 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 AR 117 2014 1 14 10 14-18 |
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10.1007/s10512-014-9881-5 doi (DE-627)OLC2060873215 (DE-He213)s10512-014-9881-5-p DE-627 ger DE-627 rakwb eng 530 VZ Nevinitsa, V. A. verfasserin aut Analysis of the Possibilities of Developing a Molten-Salt Blanket for a Subcritical Demonstration Reactor 2014 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media New York 2014 The possibilities of developing a demonstration electronuclear facility with a subcritical reactor, proton accelerator and neutron source in the form of a target unit are analyzed. This facility is proposed for working out key technologies for utilizing Np, Am, and Cm obtained from spent nuclear fuel as well as the production of 233U and 233Pa in the blanket of a molten-salt reactor. The transmutation technologies are important for bringing the raw isotopes 238U and 232Th into energy production, closing the nuclear fuel cycle, reducing the amounts of buried transuranium elements, and increasing the nuclear fuel utilization efficiency. Thorium Fuel Cycle Spend Fuel Spend Nuclear Fuel Nuclear Fuel Cycle Dudnikov, A. A. aut Frolov, A. A. aut Lubina, A. S. aut Sedov, A. A. aut Blandinskii, V. Yu. aut Balanin, A. L. aut Belov, I. A. aut Fomichenko, P. A. aut Subbotin, A. S. aut Subbotin, S. A. aut Alekseev, P. N. aut Voloshchenko, A. M. aut Titarenko, Yu. E. aut Batyaev, V. F. aut Rogov, V. I. aut Pavlov, K. V. aut Titarenko, A. Yu. aut Kulevoy, T. V. aut Gerasimov, K. A. aut Didenko, A. N. aut Polozov, S. M. aut Enthalten in Atomic energy Springer US, 1992 117(2014), 1 vom: 14. Okt., Seite 14-18 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:117 year:2014 number:1 day:14 month:10 pages:14-18 https://doi.org/10.1007/s10512-014-9881-5 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 AR 117 2014 1 14 10 14-18 |
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10.1007/s10512-014-9881-5 doi (DE-627)OLC2060873215 (DE-He213)s10512-014-9881-5-p DE-627 ger DE-627 rakwb eng 530 VZ Nevinitsa, V. A. verfasserin aut Analysis of the Possibilities of Developing a Molten-Salt Blanket for a Subcritical Demonstration Reactor 2014 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media New York 2014 The possibilities of developing a demonstration electronuclear facility with a subcritical reactor, proton accelerator and neutron source in the form of a target unit are analyzed. This facility is proposed for working out key technologies for utilizing Np, Am, and Cm obtained from spent nuclear fuel as well as the production of 233U and 233Pa in the blanket of a molten-salt reactor. The transmutation technologies are important for bringing the raw isotopes 238U and 232Th into energy production, closing the nuclear fuel cycle, reducing the amounts of buried transuranium elements, and increasing the nuclear fuel utilization efficiency. Thorium Fuel Cycle Spend Fuel Spend Nuclear Fuel Nuclear Fuel Cycle Dudnikov, A. A. aut Frolov, A. A. aut Lubina, A. S. aut Sedov, A. A. aut Blandinskii, V. Yu. aut Balanin, A. L. aut Belov, I. A. aut Fomichenko, P. A. aut Subbotin, A. S. aut Subbotin, S. A. aut Alekseev, P. N. aut Voloshchenko, A. M. aut Titarenko, Yu. E. aut Batyaev, V. F. aut Rogov, V. I. aut Pavlov, K. V. aut Titarenko, A. Yu. aut Kulevoy, T. V. aut Gerasimov, K. A. aut Didenko, A. N. aut Polozov, S. M. aut Enthalten in Atomic energy Springer US, 1992 117(2014), 1 vom: 14. Okt., Seite 14-18 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:117 year:2014 number:1 day:14 month:10 pages:14-18 https://doi.org/10.1007/s10512-014-9881-5 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 AR 117 2014 1 14 10 14-18 |
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Nevinitsa, V. A. Dudnikov, A. A. Frolov, A. A. Lubina, A. S. Sedov, A. A. Blandinskii, V. Yu. Balanin, A. L. Belov, I. A. Fomichenko, P. A. Subbotin, A. S. Subbotin, S. A. Alekseev, P. N. Voloshchenko, A. M. Titarenko, Yu. E. Batyaev, V. F. Rogov, V. I. Pavlov, K. V. Titarenko, A. Yu. Kulevoy, T. V. Gerasimov, K. A. Didenko, A. N. Polozov, S. M. |
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analysis of the possibilities of developing a molten-salt blanket for a subcritical demonstration reactor |
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Analysis of the Possibilities of Developing a Molten-Salt Blanket for a Subcritical Demonstration Reactor |
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The possibilities of developing a demonstration electronuclear facility with a subcritical reactor, proton accelerator and neutron source in the form of a target unit are analyzed. This facility is proposed for working out key technologies for utilizing Np, Am, and Cm obtained from spent nuclear fuel as well as the production of 233U and 233Pa in the blanket of a molten-salt reactor. The transmutation technologies are important for bringing the raw isotopes 238U and 232Th into energy production, closing the nuclear fuel cycle, reducing the amounts of buried transuranium elements, and increasing the nuclear fuel utilization efficiency. © Springer Science+Business Media New York 2014 |
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The possibilities of developing a demonstration electronuclear facility with a subcritical reactor, proton accelerator and neutron source in the form of a target unit are analyzed. This facility is proposed for working out key technologies for utilizing Np, Am, and Cm obtained from spent nuclear fuel as well as the production of 233U and 233Pa in the blanket of a molten-salt reactor. The transmutation technologies are important for bringing the raw isotopes 238U and 232Th into energy production, closing the nuclear fuel cycle, reducing the amounts of buried transuranium elements, and increasing the nuclear fuel utilization efficiency. © Springer Science+Business Media New York 2014 |
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The possibilities of developing a demonstration electronuclear facility with a subcritical reactor, proton accelerator and neutron source in the form of a target unit are analyzed. This facility is proposed for working out key technologies for utilizing Np, Am, and Cm obtained from spent nuclear fuel as well as the production of 233U and 233Pa in the blanket of a molten-salt reactor. The transmutation technologies are important for bringing the raw isotopes 238U and 232Th into energy production, closing the nuclear fuel cycle, reducing the amounts of buried transuranium elements, and increasing the nuclear fuel utilization efficiency. © Springer Science+Business Media New York 2014 |
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