Assimilation of a Closed Uranium-Plutonium Nuclear Fuel Cycle Based on Fast Reactors With Liquid-Metal Coolant

被引：0
|
作者：
Radchenko, M. V. [1 ]
Shadrin, A. Yu [1 ]
Poluektov, P. P. [1 ]
Shmidt, O. V. [1 ]
Tuzov, A. A. [2 ]
机构：
[1] Bochvar All Russia Res Inst Inorgan Mat VNIINM, Moscow, Russia
[2] Rosatom State Corp, Moscow, Russia
来源：
ATOMIC ENERGY | 2013年 / 115卷 / 02期
关键词：
Plutonium; Nuclear Fuel; Fast Reactor; Thermal Reactor; Fuel Cycle;
D O I：
10.1007/s10512-013-9752-5
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The advantages of fast reactors are presented and a sequence of actions for solving the important problem of assimilating a closed NFC with uranium-plutonium fuel based on fast reactors with liquid-metal coolant is examined taking account of the problems of modern nuclear power based on thermal reactors.
引用
收藏
页码：78 / 82
页数：5
相关论文
共 50 条
  • [31] Certain Aspects of Using 15N-Enriched Mixed Uranium-Plutonium Nitride Fuel in a Fast-Reactor Fuel Cycle
    A. V. Lizunov
    A. A. Semenov
    A. S. Anikin
    A. V. Moiseev
    A. P. Zhirnov
    E. O. Soldatov
    Atomic Energy, 2022, 132 : 1 - 7
  • [32] Certain Aspects of Using 15N-Enriched Mixed Uranium-Plutonium Nitride Fuel in a Fast-Reactor Fuel Cycle
    Lizunov, A., V
    Semenov, A. A.
    Anikin, A. S.
    Moiseev, A., V
    Zhirnov, A. P.
    Soldatov, E. O.
    ATOMIC ENERGY, 2022, 132 (01) : 1 - 7
  • [33] MULTICHANNEL MODEL FOR FUEL-COOLANT INTERACTION IN A LIQUID-METAL FAST BREEDER REACTOR SUBASSEMBLY
    MEHR, K
    KOTTOWSKI, HM
    GOLDAMMER, H
    NUCLEAR TECHNOLOGY, 1979, 46 (02) : 362 - 368
  • [34] Nuclear Non-Proliferation Security on Exportation of Fast Reactors with a Closed Fuel Cycle
    Gorin, N. V.
    Voloshin, N. P.
    Churikov, Yu. I.
    Chebeskov, A. N.
    Kuchinov, V. P.
    Vasiliev, A. P.
    Moiseev, A. V.
    Shepelev, S. F.
    Skvortsov, D. A.
    Zhurin, S. I.
    Shidlovskiy, V. V.
    Krivtsov, A. V.
    ATOMIC ENERGY, 2021, 130 (01) : 53 - 56
  • [35] Nuclear Non-Proliferation Security on Exportation of Fast Reactors with a Closed Fuel Cycle
    N. V. Gorin
    N. P. Voloshin
    Yu. I. Churikov
    A. N. Chebeskov
    V. P. Kuchinov
    A. P. Vasiliev
    A. V. Moiseev
    S. F. Shepelev
    D. A. Skvortsov
    S. I. Zhurin
    V. V. Shidlovskiy
    A. V. Krivtsov
    Atomic Energy, 2021, 130 : 53 - 56
  • [36] Purification of Uranium-Plutonium Extract of VVER-1000 Spent Nuclear Fuel from Fission Products by Liquid Chromatography
    Volk, V. I.
    Podrezova, L. N.
    Alekseenko, V. N.
    D'yachenko, A. S.
    ATOMIC ENERGY, 2021, 129 (03) : 141 - 143
  • [37] Purification of Uranium-Plutonium Extract of VVER-1000 Spent Nuclear Fuel from Fission Products by Liquid Chromatography
    V. I. Volk
    L. N. Podrezova
    V. N. Alekseenko
    A. S. D’yachenko
    Atomic Energy, 2021, 129 : 141 - 143
  • [38] NEUTRONIC DESIGN OF URANIUM-PLUTONIUM NITRIDE FUEL-BASED GAS-COOLED FAST REACTOR (GFR)
    Novalianda, S.
    Ariani, M.
    Monado, F.
    Su'ud, Z.
    JURNAL PENDIDIKAN FISIKA INDONESIA-INDONESIAN JOURNAL OF PHYSICS EDUCATION, 2018, 14 (02): : 92 - 98
  • [39] EXPERIMENTAL STUDY OF THE WALL BOUNDARY LAYER "HEAVY LIQUID-METAL COOLANT - CONSTRUCTIONAL MATERIAL" AS APPLIED TO FAST REACTORS
    Makhov, Kirill
    Beznosov, Aleksander V.
    Bokova, Tatyana
    Shumilkov, Artem
    Chernysh, Aleksei
    Knyazev, Alexander Vladimirovich
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 5, 2014,
  • [40] FISSION GAS RELEASE FROM FAILED FUEL RODS IN LIQUID-METAL FAST BREEDER REACTORS
    CARELLI, MD
    COFFIELD, RD
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (NAPR): : 28 - &
12345