Fuel cycle of a brest fast reactor in an americium transmutation regime

被引:0
|
作者
Kvaratskheli A.Yu. [1 ]
Knyazev A.P. [1 ]
Konev V.N. [1 ]
Kochurov B.P. [1 ]
机构
[1] State Sci. Ctr. of the Russ. Fed., A. I. Alikhanov Inst. Theor./Exp. P.
关键词
Storage Time; Fission Product; Average Multiplication; Americium; Fuel Cycle;
D O I
10.1007/s10512-005-0036-6
中图分类号
学科分类号
摘要
The characteristics of a closed equilibrium cycle for a BREST fast reactor are calculated (using the BREST-OD-300 model) for the americium transmutation regime with a 5% h.a. load. For the same average multiplication ratio as in the standard equilibrium cycle, the reactivity would, vary by 1% over a 1-yr microrun, which requires partial reloadings approximately every month. The spectral part of the void coefficient of reactivity is 20% higher than for the standard cycle. Sixty-one kilograms of americium are transmuted in 1 yr of reactor operation. For high 238Pu content in the fuel, the americium transmutes predominantly into fission products. Americium in the spent fuel from eight VVÉR-1000 reactors can be transmuted in a similar regime in a BREST-1200 reactor (with spent-fuel storage time 30 yr and a high americium content due to 241Pu decay). © 2004 Springer Science+Business Media, Inc.
引用
下载
收藏
页码:593 / 597
页数:4
相关论文
共 50 条
  • [31] THE FAST BREEDER REACTOR-FUEL CYCLE
    ALLARDICE, RH
    MEGY, J
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 48 : 146 - 152
  • [32] Possibilities of BREST reactors and transmutation fuel cycle under conditions implementing modern plans for the development of nuclear power
    Lopatkin, A. V.
    Orlov, V. V.
    Lukasevich, I. B.
    Zaiko, I. V.
    Ganev, I. Kh.
    ATOMIC ENERGY, 2007, 103 (01) : 509 - 517
  • [33] A subcritical, helium-cooled fast reactor for the transmutation of spent nuclear fuel
    Stacey, W. M.
    Abbasi, Z.
    Boyd, C. J.
    Bridges, A. H.
    Burgett, E. A.
    Cymbor, M. W.
    Fowler, S. W.
    Jones, A. T.
    Kelm, R. S.
    Kern, B. J.
    Lassiter, D. B.
    Maddox, J. A.
    Murphy, W. B.
    Park, H.
    Pounders, J. M.
    Preston, J. R.
    NUCLEAR TECHNOLOGY, 2006, 156 (01) : 99 - 123
  • [34] Possibilities of BREST reactors and transmutation fuel cycle under conditions implementing modern plans for the development of nuclear power
    A. V. Lopatkin
    V. V. Orlov
    I. B. Lukasevich
    I. V. Zaiko
    I. Kh. Ganev
    Atomic Energy, 2007, 103 : 509 - 517
  • [35] Transmutation characteristics in thermal and fast neutron spectra: application to americium
    Berthou, V
    Degueldre, C
    Magill, J
    JOURNAL OF NUCLEAR MATERIALS, 2003, 320 (1-2) : 156 - 162
  • [36] FAST-REACTOR ACTINOID TRANSMUTATION
    GOLUBEV, VI
    DOLGOV, VV
    DULIN, VA
    ZVONAREV, AV
    SMETANIN, EY
    KOCHETKOV, LA
    KOROBEINIKOV, VV
    LIFOROV, VG
    MANTUROV, GN
    MATVEENKO, IP
    TSIBULYA, AM
    ATOMIC ENERGY, 1993, 74 (01) : 83 - 84
  • [37] SENSITIVITY ANALYSIS FOR FAST-REACTOR FUEL CYCLE
    SIERRA, JM
    BECKER, M
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 535 - 536
  • [38] The Effect Assessment for Fast Reactor Fuel Cycle Deployment
    Shiotani, Hiroki
    Mukaida, Kyoko
    Ono, Kiyoshi
    Namba, Takashi
    3RD INTERNATIONAL CONFERENCE ON ASIAN NUCLEAR PROSPECTS (ANUP2012), 2013, 39 : 33 - 42
  • [39] Hypothetical integration of a fast reactor to the fuel cycle in Slovakia
    Zajac, Radoslav
    Darilek, Petr
    Necas, Vladimir
    ANNALS OF NUCLEAR ENERGY, 2011, 38 (08) : 1705 - 1714
  • [40] SYNBURN - FAST-REACTOR FUEL CYCLE CODE
    PIZZICA, PA
    MENELEY, DA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 22 (NOV16): : 701 - 702