Abstract
The fast-neutron breeder reactor is the principal means now envisaged of exploiting the very large resource of energy residing in the naturally abundant isotope of uranium , 238 U. Extensive research and development programmes are being carried out in a num ber of countries to realize this potential. There are about a dozen substantial reactors operating; and wide-ranging supporting programmes include fuel processing and development, and safety and environmental issues. The purpose of this Discussion Meeting is to present the principal recent scientific and engineering results of these world-wide program m es; and, in the final session, to discuss the future trends in this research and its utilization.
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