Choice of the capacity of a fast reactor for nuclear power



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Topic: Science > Physics
User: "ayaz"
Date: 26 Jan 2008 02:57:11 AM
Object: Choice of the capacity of a fast reactor for nuclear power
N. N. Ponomarev-Stepnoi1 and V. F. Tsibul'skii1
(1) Russian Science Center Kurchatov Institute, Russia
Received: 13 April 2007
Abstract Analytical assessments, associated with the choice of the
unit capacity of a serially built fast reactor under conditions of the
future advancement of nuclear power, are presented. It is shown that
considering the limited resources of natural uranium, the development
of a reliable raw materials base must be based on the development of
fast reactors with expanded breeding of fuel and fuel cycle closure.
Since fast reactors, together with energy production, are also
producers of new fuel, their parameters must be optimized taking
account of this factor on the basis of systems analysis. Calculations
show that the optimal capacity for fast reactors is in the 1 GW
range.
__________
Translated from Atomnaya =C9nergiya, Vol. 103, No. 2, pp. 83-88, August,
2007.
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References
1. V. V. Orlov, V. N. Leonov, A. V. Lopatkin, et al., "Construction of
the BREST reactor. Experimental work validating the concept of BREST
reactors. Results and plans," in: International Seminar on Inherently
Safe Fast Reactor and Fuel Cycle for Large-Scale Power Production.
Fuel Balance, Economics, Wastes, Nonproliferation, Minatom, Moscow
(2000), pp. 7-19.
2. S. M. Feinberg, "Gas-cooled breeders as an alternative to liquid-
metal coolant. Ideology of hard and soft spectra," Reports at the
Conference of Experts at IAEA on Gas-Cooled Fast Reactors, Minsk
(1972). IAEA, Vienna (1973), pp. 21-63.
3. N. N. Ponomarev-Stepnoi, E. S. Glushkov, V. N. Grebennik, et al.,
"Engineering and physical problems of gas-cooled fast breeder
reactors," ibid., pp. 191-235.
4. V. I. Kostin and B. A. Vasil'ev, "Problems of constructing BN-800
and the possibility of developing advanced fast reactors," At. =C9nerg.,
102, No. 1, 21-26 (2007).
.

 

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