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Computational Survey of Idealized Fast Breeder Reactors

William H. Roach

Nuclear Science and Engineering / Volume 8 / Number 6 / Pages 621-651

December 1960

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A calculational survey of idealized fast breeder reactors is reported. Representative fuel (Pu239, U235, U233), fertile (U238, Th232), structural (stainless steel), and coolant (sodium) materials are used in the calculations, references providing information as to the substitutional effect of other materials. The calculational method is defined, input parameters are discussed, and results such as critical mass, critical volume, initial breeding ratios, and spectral indices for the reactors are tabulated.

 
 
 
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