Abstract
This paper gives data on the feasibility of using U233 and thorium in a breeding-reactor system. From the viewpoint of doubling time, the most promising method is the simultaneous use of U233-Th and Pu239−U238 in a mixedffuel cycle in fast reactors; the thorium being distributed in the screens and the U233, Pu239 and U238 in the cores. Consumption and breeding of U233 and Pu239 is arranged so that their amounts remain in constant ratio. The doubling time of a fast-reactor system working with a mixedfuel cycle is considerably less than that of reactors using only U233 or thorium. The main raw material is thorium. A method is indicated for obtaining isotopically-pure U233 containing ~10−4% U232.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
Literature Cited
L. P. Abagyan et al., Group Constants for Reactor Calculations [in Russian], Gosatomizdat, Moscow (1964).
A. I. Leipunskii et al., Report No. 369, presented by the USSR to the Third International Conference on the Peaceful Uses of Atomic Energy, Geneva (1964).
M. Benedict and T. Pickford, Chemical Technology of Nuclear Materials [Russian translation], Atomizdat, Moscow (1960).
Additional information
Translated from Atomnaya Énergiya, Vol. 18, No. 4, pp. 342–350, April, 1965
Rights and permissions
About this article
Cite this article
Leipunskii, A.I., Kazachkovskii, O.D., Shikhov, S.B. et al. Feasibility of using thorium in fast power reactors. At Energy 18, 434–441 (1965). https://doi.org/10.1007/BF01115962
Received:
Issue Date:
DOI: https://doi.org/10.1007/BF01115962