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.
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页码:593 / 597
页数:4
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