Abstract
Breeder reactors with a fast neutron spectrum have a sufficiently high breeding ratio to allow independence of any external supply of fissile material in practical operation. The U-238/Pu-239 or the Th-232/U-233 conversion processes enable this type of reactor to utilize natural uranium or thorium theoretically with 100% efficiency and practically, including losses in the fuel cycle, with an efficiency in excess of 60%. This is a factor of 100 higher than the fuel utilization in present standard LWR’s without reprocessing, and approximately a factor of 25 to 50 higher than in converter reactors operating with high conversion ratios and in the recycling mode (see Section 2.6 and Chapter 6).
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Kessler, G. (1983). Breeder Reactors with a Fast Neutron Spectrum. In: Nuclear Fission Reactors. Topics in Energy. Springer, Vienna. https://doi.org/10.1007/978-3-7091-7622-1_5
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DOI: https://doi.org/10.1007/978-3-7091-7622-1_5
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